Nuclear refinery - advanced energy complex for electricity generation, clean fuel production, and heat supply

International Nuclear Information System (INIS)

McDonald, C.F.

1992-01-01

In planning for increased U.S. energy users' demand after the year 2000 there are essentially four salient vectors: (1) reduced reliance on imported crude oil; (2) provide a secure supply with stable economics; (3) supply system must be in concert with improved environment goals; and (4) maximum use to be made of indigenous resources. For the last decade of this century the aforementioned will likely be met by increasing utilization of natural gas. Early in the next century, however, in the U.S. and the newly industrializing nations, the ever increasing energy demand will only be met by the combined use of uranium and coal. The proposed nuclear refinery concept is an advanced energy complex that has at its focal point an advanced modular helium reactor (MHR). This nuclear facility, together with a coal feedstock, could contribute towards meeting the needs of the four major energy sectors in the U.S., namely electricity, transportation, industrial heating and chemical feedstock, and space and water heating. Such a nuclear/coal synergistic system would be in concert with improved air quality goals. This paper discusses the major features and multifaceted operation of a nuclear refinery concept, and identifies the enabling technologies needed for such an energy complex to become a reality early in the 21st century. (Author)

Metal complexation in near field conditions of nuclear waste repository - stability constant of copper complexation with cellulose degradation products, in alkaline conditions

International Nuclear Information System (INIS)

Guede, Kipre Bertin

2005-11-01

Copper is a stable element and spent fuel component which constitutes the radioactive waste. The reaction of Copper with cellulose degradation products in alkaline conditions was performed to mimic what occurs in near field conditions of nuclear waste repository. From the characteristics of Cu (II), this thesis aims at inferring the behaviour of radionuclides vis a vis the degradation products of cellulose. The contribution of the present work is therefore the assessment of the stability of the major cellulose degradation product, its affinity for Copper and the extent of the complexation function 13 between Cu (II) and the organic moieties. The formation of cellulose degradation products was followed by measurement of p11, Conductivity, Angle of rotation, relative abundance of aliphatics and aromatics (E4/E6 ) aid by UV-visible spectroscopy. The TOC was determined using the Walkley and Black titration after respectively 31 weeks and 13 weeks of degradation for the reaction mixtures T and A, N. The stability of the major degradation products gave the following figures: ISA(A): - 13 43.39 <ΔG -10639.88 ISA(N): - Ii 436.45<ΔG< -9103.6. The study of the characteristics of Gluconic Acid, as a model compound, was carried out in an attempt to give a general picture of the roper ties of cellulose degradation products. The Complexation between Cu (II) and the organic ligand (Cellulose degradation products) was performed using UV-visible spectroscopy and Ion Distribution technique. The Log B value obtained from the complexation studies at 336 nm for 1 = 0. I Ni NaClO4 and I = 0.01 M NaClO4, falls within a range of 3.48 to 3.74 for the standard reference material (Gluconic Acid), and within I .87 to 2.3 I, and I .6 to 2.01, respectively for the degradation Products ISA (A) and ISA(N). The ion distribution studies showed that: • In (he absence of the degradation product ISA and at pH = 3.68. 56. 17 % of Cu (II) was bound to the resin. • In the presence of ISA and at 2

Design features of isotope production facility at Inshas cyclotron complex. Vol. 1

Energy Technology Data Exchange (ETDEWEB)

Comsan, M N [Nuclear Research Center, Atomic Energy Aurhority, Cairo, (Egypt)

1996-03-01

The nuclear research center, AEA, Egypt is erecting at its Inshas campus cyclotron complex for multidisciplinary use for research and application. The complex is to utilize a russian made AVF cyclotron accelerator of the type MGC-20 with MeV protons. Among its applications, the accelerator will be used for the production of short lived cyclotron isotopes. This article presents a concise description of the design features of isotope production facility to be annexed to the complex layout, schemes for radio waste, ventilation, and air conditioning systems. 2 figs., 2 tabs.

25 years of NDE in fabrication of zirconium alloy mill products and nuclear fuel in the Nuclear Fuel Complex

International Nuclear Information System (INIS)

Mistry, R.K.; Laxminarayana, B.; Srivastava, R.K.

1996-01-01

Failure of nuclear fuel is highly undesirable from both economic and operational aspects. Hence all the components require rigorous QC and inspection checks. NDT plays a major role in assuring the quality of the products both at final and intermediate stages. This paper gives an overall review of NDT methods employed in achieving the integrity of nuclear products. The NDE procedures followed in NFC are visual inspection, radiography, penetrant testing, eddy current testing, ultrasonic testing and helium leak testing. NFC's quality assurance programme is organised to achieve the desired objectives by carrying out in process and final inspection at all critical steps of fabrication. (author)

Analysis of the matrix structure of the Nuclear Weapons Complex waste minimization and hazard reduction program

International Nuclear Information System (INIS)

Churnetski, S.R.

1991-01-01

Two of the primary goals of this program in waste minimization that the major waste problems facing the Nuclear Weapons Complex (NWC) are being addressed systematically and to prevent duplication of effort by forming an integrated approach across the complex. Production, disposal, and the hazards of both the wastes and the in-process chemicals used were to be studied. The eight waste streams chosen (electroplating, miscellaneous, mixed, plutonium, polymers, solvents, tritium, and uranium) were deemed to be the most serious problems facing the Nuclear Weapons Complex

A combined hydro-nuclear-solar project for electric power production

International Nuclear Information System (INIS)

Yiftah, S.

1985-01-01

Some of the main, general-perspective themes of Dr. Alvin Weinberg's leadership and long and varied work are: the effect of present and future nuclear energy projects on society, not only in the United States but throughout the world; analysis, comparison, and combination of various sources of energy; extensive multiple use of nuclear energy complexes (so-called NUPLEX, for nuclear complex) for various areas of the world; and use of ''Big Technology'' and ''Big Science'' for solving, or helping to solve, political problems. A combined hydro-nuclear-solar project for electric power production is discussed, as well as two other energy-related engineering projects. Some of the projects originated or were inspired by work done at the Oak Ridge National Laboratory under the leadership of Dr. Alvin Weinberg. Also reported are the technical characteristics and interrelationships of the three components of the envisaged hydronuclear-solar project

Engineering and technology in the deconstruction of nuclear materials production facilities

International Nuclear Information System (INIS)

Kingsley, R.S.; Reynolds, W.E.; Heffner, D.C.

1996-01-01

Technology and equipment exist to support nuclear facility deactivation, decontamination, and decommissioning. In reality, this statement is not surprising because the nuclear industry has been decontaminating and decommissioning production plants for decades as new generations of production technology were introduced. Since the 1950s, the Babcock and Wilcox Company (B ampersand W) has operated a number of nuclear materials processing facilities to manufacture nuclear fuel for the commercial power industry and the U.S. Navy. These manufacturing facilities included a mixed oxide (PuO 2 -UO 2 ) nuclear fuel manufacturing plant, low- and high-enriched uranium (HEU/LEU) chemical and fuel plants, and fuel assembly plants. In addition, B ampersand W designed and build a major nuclear research center in Lynchburg, Virginia, to support these nuclear fuel manufacturing activities and to conduct nuclear power research. These nuclear research facilities included two research reactors, a hot-cell complex for nuclear materials research, four critical experiment facilities, and a plutonium fuels research and development facility. This article describes the B ampersand W deactivation, decomtanimation, and decommisioning program

Hazards ahead: Managing cleanup worker health and safety at the nuclear weapons complex. Background paper

International Nuclear Information System (INIS)

1993-02-01

Cold War nuclear weapons production has left a legacy of environmental contamination that is unprecented in scope and complexity. The Department of Energy has begun cleaning up pollution at the Nuclear Weapons Complex (NWC)--an expensive, decades-long task that will require a workforce numbering tens of thousands of scientists, technicians, and laborers. Protecting their health and safety must be a major goal of the cleanup effort. Achieving the goal will require DOE to successfully confront significant technical and managerial challenges, but it also poses a unique opportunity to advance state-of-the-art occupational health and safety technologies and practices. The report provides an evaluation of environmental restoration and waste management at the DOE Nuclear Weapons Complex. It examines risks workers might face in cleaning up contamination at the complex and evaluates the effectiveness of DOE's occupational safety and health programs for cleanup workers

Nuclear industrial and power complex of Kazakhstan

International Nuclear Information System (INIS)

Shemanskiy, V.A.; Cherepnin, Yu.S.; Zelenski, D.I.; Papafanasopulo, G.A.

1997-01-01

While selecting the national power supply strategy of economic potential development four factors are laid in the basis of discussions and technical and economic decisions: effect either power complexes on people health, consequences environmental, economics and resources existence. Atomic power requires the balanced approach to power politics which, by that, avoids the dependence on any energy source. The existing electric power generation structure in Kazakhstan is Featured by the following numbers: -TEPP on coal - 79%; - TEPP on gas-black-oil fuel - 12-13%; - HEPP - 6-7%; - Atomic PP - about 0.7%. The ground for nuclear power development is considerable uranium deposits and rather developed atomic industry. Kazakhstan atomic industry includes: - uranium extractive enterprise - State Holding Company 'Tselinnyi Mining-Chemical Plant' (SHC 'TCMP'), Stepnoy Ore Division (SOD), Central ore Division 6 (COD 6), KASKOR (Aktau); - plant on fuel pellets production for APP (JSC 'UMP'); - plants on production of rare and rare-earth metals - Irtysh Chemical and Metallurgical (JSC 'CMP') and Ulba Metallurgical Plant (JSC 'UMP'); - Mangyshlak Power Plant (MAEK); - Scientific Complex of NNC RK of Ministry of Science-Academy of Science. About 25% of world deposits and uranium resources are concentrated in Kazakhstan bowels. The scientific potential of atomic production complex of the Republic of Kazakhstan is concentrated in NNC RK divisions (IAE and INP) and at JSC 'UMP' and MAEK enterprises. Ministry Energy and Nature Resources is a Board responsible for the development of atomic industry and power branches. Atomic Energy Agency of the Republic Kazakhstan performs the independent effective state supervision and control providing safety of atomic industry power installations operation

On the benefits of an integrated nuclear complex for Nevada

International Nuclear Information System (INIS)

Blink, J.A.; Halsey, W.G.

1994-01-01

An integrated nuclear complex is proposed for location at the Nevada Test Site. In addition to solving the nuclear waste disposal problem, this complex would tremendously enhance the southern Nevada economy, and it would provide low cost electricity to each resident and business in the affected counties. Nuclear industry and the national economy would benefit because the complex would demonstrate the new generation of safer nuclear power plants and revitalize the industry. Many spin-offs of the complex would be possible, including research into nuclear fusion and a world class medical facility for southern Nevada. For such a complex to become a reality, the cycle of distrust between the federal government and the State of Nevada must be broken. The paper concludes with a discussion of implementation through a public process led by state officials and culminating in a voter referendum

Integrative structure and functional anatomy of a nuclear pore complex

Science.gov (United States)

Kim, Seung Joong; Fernandez-Martinez, Javier; Nudelman, Ilona; Shi, Yi; Zhang, Wenzhu; Raveh, Barak; Herricks, Thurston; Slaughter, Brian D.; Hogan, Joanna A.; Upla, Paula; Chemmama, Ilan E.; Pellarin, Riccardo; Echeverria, Ignacia; Shivaraju, Manjunatha; Chaudhury, Azraa S.; Wang, Junjie; Williams, Rosemary; Unruh, Jay R.; Greenberg, Charles H.; Jacobs, Erica Y.; Yu, Zhiheng; de La Cruz, M. Jason; Mironska, Roxana; Stokes, David L.; Aitchison, John D.; Jarrold, Martin F.; Gerton, Jennifer L.; Ludtke, Steven J.; Akey, Christopher W.; Chait, Brian T.; Sali, Andrej; Rout, Michael P.

2018-03-01

Nuclear pore complexes play central roles as gatekeepers of RNA and protein transport between the cytoplasm and nucleoplasm. However, their large size and dynamic nature have impeded a full structural and functional elucidation. Here we determined the structure of the entire 552-protein nuclear pore complex of the yeast Saccharomyces cerevisiae at sub-nanometre precision by satisfying a wide range of data relating to the molecular arrangement of its constituents. The nuclear pore complex incorporates sturdy diagonal columns and connector cables attached to these columns, imbuing the structure with strength and flexibility. These cables also tie together all other elements of the nuclear pore complex, including membrane-interacting regions, outer rings and RNA-processing platforms. Inwardly directed anchors create a high density of transport factor-docking Phe-Gly repeats in the central channel, organized into distinct functional units. This integrative structure enables us to rationalize the architecture, transport mechanism and evolutionary origins of the nuclear pore complex.

Integrative structure and functional anatomy of a nuclear pore complex.

Science.gov (United States)

Kim, Seung Joong; Fernandez-Martinez, Javier; Nudelman, Ilona; Shi, Yi; Zhang, Wenzhu; Raveh, Barak; Herricks, Thurston; Slaughter, Brian D; Hogan, Joanna A; Upla, Paula; Chemmama, Ilan E; Pellarin, Riccardo; Echeverria, Ignacia; Shivaraju, Manjunatha; Chaudhury, Azraa S; Wang, Junjie; Williams, Rosemary; Unruh, Jay R; Greenberg, Charles H; Jacobs, Erica Y; Yu, Zhiheng; de la Cruz, M Jason; Mironska, Roxana; Stokes, David L; Aitchison, John D; Jarrold, Martin F; Gerton, Jennifer L; Ludtke, Steven J; Akey, Christopher W; Chait, Brian T; Sali, Andrej; Rout, Michael P

2018-03-22

Nuclear pore complexes play central roles as gatekeepers of RNA and protein transport between the cytoplasm and nucleoplasm. However, their large size and dynamic nature have impeded a full structural and functional elucidation. Here we determined the structure of the entire 552-protein nuclear pore complex of the yeast Saccharomyces cerevisiae at sub-nanometre precision by satisfying a wide range of data relating to the molecular arrangement of its constituents. The nuclear pore complex incorporates sturdy diagonal columns and connector cables attached to these columns, imbuing the structure with strength and flexibility. These cables also tie together all other elements of the nuclear pore complex, including membrane-interacting regions, outer rings and RNA-processing platforms. Inwardly directed anchors create a high density of transport factor-docking Phe-Gly repeats in the central channel, organized into distinct functional units. This integrative structure enables us to rationalize the architecture, transport mechanism and evolutionary origins of the nuclear pore complex.

Supplying the nuclear arsenal: Production reactor technology, management, and policy, 1942--1992

Energy Technology Data Exchange (ETDEWEB)

Carlisle, R.P.; Zenzen, J.M.

1994-01-01

This book focuses on the lineage of America`s production reactors, those three at Hanford and their descendants, the reactors behind America`s nuclear weapons. The work will take only occasional sideways glances at the collateral lines of descent, the reactor cousins designed for experimental purposes, ship propulsion, and electric power generation. Over the decades from 1942 through 1992, fourteen American production reactors made enough plutonium to fuel a formidable arsenal of more than twenty thousand weapons. In the last years of that period, planners, nuclear engineers, and managers struggled over designs for the next generation of production reactors. The story of fourteen individual machines and of the planning effort to replace them might appear relatively narrow. Yet these machines lay at the heart of the nation`s nuclear weapons complex. The story of these machines is the story of arming the winning weapon, supplying the nuclear arms race. This book is intended to capture the history of the first fourteen production reactors, and associated design work, in the face of the end of the Cold War.

Enhancing Safety Culture in Complex Nuclear Industry Projects

International Nuclear Information System (INIS)

Gotcheva, N.

2016-01-01

This paper presents an on-going research project “Management principles and safety culture in complex projects” (MAPS), supported by the Finnish Research Programme on Nuclear Power Plant Safety 2015-2018. The project aims at enhancing safety culture and nuclear safety by supporting high quality execution of complex projects in the nuclear industry. Safety-critical industries are facing new challenges, related to increased outsourcing and complexity in technology, work tasks and organizational structures (Milch and Laumann, 2016). In the nuclear industry, new build projects, as well as modernisation projects are temporary undertakings often carried out by networks of companies. Some companies may have little experience in the nuclear industry practices or consideration of specific national regulatory requirements. In large multinational subcontractor networks, the challenge for assuring nuclear safety arises partly from the need to ensure that safety and quality requirements are adequately understood and fulfilled by each partner. Deficient project management practices and unsatisfactory nuclear safety culture in project networks have been recognised as contributing factors to these challenges (INPO, 2010). Prior evidence indicated that many recent major projects have experienced schedule, quality and financial challenges both in the nuclear industry (STUK, 2011) and in the non-nuclear domain (Ahola et al., 2014; Brady and Davies, 2010). Since project delays and quality issues have been perceived mainly as economic problems, project management issues remain largely understudied in safety research. However, safety cannot be separated from other performance aspects if a systemic view is applied. Schedule and quality challenges may reflect deficiencies in coordination, knowledge and competence, distribution of roles and responsibilities or attitudes among the project participants. It is increasingly understood that the performance of the project network in all

Nuclear power complexes and economic-ecological problems of nuclear power development

International Nuclear Information System (INIS)

Dollezhal', N.A.; Bobolovich, V.N.; Emel'yanov, I.Ya.

1977-01-01

The effect of constructing NPP's at separate sites in densely populated areas on economic efficiency of nuclear power and its ecological implications has been investigated. Locating NPP's and nuclear fuel cycle plants at different sites results in large scale shipments of fresh and spent nuclear fuels and radioactive wastes. The fact increases the risk of a detrimental environmental impact, duration of the external fuel cycle, and worsens, in the end, nuclear power economics. The prudence of creating nuclear parks is discussed. The parks may be especially efficient if the program of developing NPP's with fast breeder reactors is a success. Comparative evaluations show that from economic standpoint deployment of nuclear parks in the European part of the USSR has no disadvantage before construction of separate NPP's and supporting fuel cycle facilities of equivalent capacity, even if the construction of nuclear parks runs dearer by 30% than assumed. The possibility for nuclear parks to meet a part of demand for ''off-peak'' energy production, district heating and process heat production is also shortly discussed

Review of the book: Vasilenko, I.Ya. Toxicology of nuclear fission products

International Nuclear Information System (INIS)

Gordeev, K.I.

2001-01-01

Review on monograph of Vasilenko, I.Ya. Toxicology of nuclear fission (Moscow, Medicine, 1999) is presented. Data of longevity full-scale investigations during nuclear explosions on the Semipalatinsk test site are given. Classified, complex investigations into the effect of nuclear fission products mixtures on different kinds of laboratory animals are described, transfer of radiobiological researches to organism of man is scientific valid. The most complicate radiobiological problem of low dose is analyzed. The being investigated monograph contains unique scientific information and makes a heavy contribution in radiobiology [ru

Crystal Structure of the Herpesvirus Nuclear Egress Complex Provides Insights into Inner Nuclear Membrane Remodeling

NARCIS (Netherlands)

Zeev-Ben-Mordehai, Tzviya; Weberruss, Marion; Lorenz, Michael; Cheleski, Juliana; Hellberg, Teresa; Whittle, Cathy; El Omari, Kamel; Vasishtan, Daven; Dent, Kyle C.; Harlos, Karl; Franzke, Kati; Hagen, Christoph; Klupp, Barbara G.; Antonin, Wolfram; Mettenleiter, Thomas C.; Gruenewald, Kay

2015-01-01

Although nucleo-cytoplasmic transport is typically mediated through nuclear pore complexes, herpesvirus capsids exit the nucleus via a unique vesicular pathway. Together, the conserved herpesvirus proteins pUL31 and pUL34 form the heterodimeric nuclear egress complex (NEC), which, in turn, mediates

Dynamic Complexity Study of Nuclear Reactor and Process Heat Application Integration

International Nuclear Information System (INIS)

Taylor, J'Tia Patrice; Shropshire, David E.

2009-01-01

This paper describes the key obstacles and challenges facing the integration of nuclear reactors with process heat applications as they relate to dynamic issues. The paper also presents capabilities of current modeling and analysis tools available to investigate these issues. A pragmatic approach to an analysis is developed with the ultimate objective of improving the viability of nuclear energy as a heat source for process industries. The extension of nuclear energy to process heat industries would improve energy security and aid in reduction of carbon emissions by reducing demands for foreign derived fossil fuels. The paper begins with an overview of nuclear reactors and process application for potential use in an integrated system. Reactors are evaluated against specific characteristics that determine their compatibility with process applications such as heat outlet temperature. The reactor system categories include light water, heavy water, small to medium, near term high-temperature, and far term high temperature reactors. Low temperature process systems include desalination, district heating, and tar sands and shale oil recovery. High temperature processes that support hydrogen production include steam reforming, steam cracking, hydrogen production by electrolysis, and far-term applications such as the sulfur iodine chemical process and high-temperature electrolysis. A simple static matching between complementary systems is performed; however, to gain a true appreciation for system integration complexity, time dependent dynamic analysis is required. The paper identifies critical issues arising from dynamic complexity associated with integration of systems. Operational issues include scheduling conflicts and resource allocation for heat and electricity. Additionally, economic and safety considerations that could impact the successful integration of these systems are considered. Economic issues include the cost differential arising due to an integrated system

Nuclear energy for hydrogen production

International Nuclear Information System (INIS)

Verfondern, K.

2007-01-01

In the long term, H 2 production technologies will be strongly focusing on CO 2 -neutral or CO 2 -free methods. Nuclear with its virtually no air-borne pollutants emissions appears to be an ideal option for large-scale centralized H 2 production. It will be driven by major factors such as production rates of fossil fuels, political decisions on greenhouse gas emissions, energy security and independence of foreign oil uncertainties, or the economics of large-scale hydrogen production and transmission. A nuclear reactor operated in the heat and power cogeneration mode must be located in close vicinity to the consumer's site, i.e., it must have a convincing safety concept of the combined nuclear/ chemical production plant. A near-term option of nuclear hydrogen production which is readily available is conventional low temperature electrolysis using cheap off-peak electricity from present nuclear power plants. This, however, is available only if the share of nuclear in power production is large. But as fossil fuel prices will increase, the use of nuclear outside base-load becomes more attractive. Nuclear steam reforming is another important near-term option for both the industrial and the transportation sector, since principal technologies were developed, with a saving potential of some 35 % of methane feedstock. Competitiveness will benefit from increasing cost level of natural gas. The HTGR heated steam reforming process which was simulated in pilot plants both in Germany and Japan, appears to be feasible for industrial application around 2015. A CO 2 emission free option is high temperature electrolysis which reduces the electricity needs up to about 30 % and could make use of high temperature heat and steam from an HTGR. With respect to thermochemical water splitting cycles, the processes which are receiving presently most attention are the sulfur-iodine, the Westinghouse hybrid, and the calcium-bromine (UT-3) cycles. Efficiencies of the S-I process are in the

Tensor Product of Polygonal Cell Complexes

OpenAIRE

Chien, Yu-Yen

2017-01-01

We introduce the tensor product of polygonal cell complexes, which interacts nicely with the tensor product of link graphs of complexes. We also develop the unique factorization property of polygonal cell complexes with respect to the tensor product, and study the symmetries of tensor products of polygonal cell complexes.

Relevance of separation science and technology to nuclear fuel complex operations

International Nuclear Information System (INIS)

Rao, S.M.; Ojha, P.B.; Rajashri, M.; Mirji, K.V.; Kalidas, R.

2004-01-01

During the last three decades at Nuclear Fuel Complex (NFC), Hyderabad, the Science and Technology of separation to produce various reactor grade materials in tonnage quantity is being practiced in the fields of Zr/Hf, U and Nb/Ta. Apart from this, the separation science is also being used in the production of various high purity materials and in the analytical field. The separation science and technology that is used in the production and characterisation of reactor grade materials has many striking differences from that of the common metals. The relevance and significance of separation science in the field of nuclear materials arises mainly due to the harmful effects w.r.t corrosion property and absorption of neutron caused by the presence of impurities, that are to be brought down to ppm or sub ppm level. In many cases low separation factors, that too from a multi component system call for effective process control at every stage of the bulk production so as to get quality product consistently. This article brings out the importance of separation science and technology and various process standardisations/developments that have been carried out at NFC, starting from laboratory scale to pilot scale and up to industrial scale production in the case of (i) Uranium refining (ii) Zr-Hf separation (iii) Ta-Nb separation and (iv) High purity materials production. (author)

Energetics of Transport through the Nuclear Pore Complex

NARCIS (Netherlands)

Ghavami, Ali; van der Giessen, Erik; Onck, Patrick R

2016-01-01

Molecular transport across the nuclear envelope in eukaryotic cells is solely controlled by the nuclear pore complex (NPC). The NPC provides two types of nucleocytoplasmic transport: passive diffusion of small molecules and active chaperon-mediated translocation of large molecules. It has been shown

Nuclear Energy Complexes: Prospects for Development and Cooperation

OpenAIRE

Vinokurov, Evgeny

2008-01-01

1. 2005–2006 was a critical period in the development of the nuclear complexes of Russian Federation and the Republic of Kazakhstan. These years have ushered in a “nuclear renaissance”. Russia’s nuclear sector was subject to a total systemic review; the Federal Target Program (FTP) allocated to it funds totaling more than USD 55 billion. A decision was taken to consolidate all nuclear assets within one state corporation. Kazakhstan implemented the “15000 tons uranium by 2010” state developmen...

Nuclear weapons complex. Weaknesses in DOE's nonnuclear consolidation plan

International Nuclear Information System (INIS)

Wells, James E. Jr.; Fenzel, William F.; Schulze, John R.; Gaffigan, Mark E.

1992-11-01

nuclear site or a national laboratory. Without a thorough analysis of all consolidation possibilities, DOE cannot be assured that its preferred option minimizes costs and technical risks. Second, the cost of consolidation is not fully known because the NCP did not include all consolidation costs. The NCP's estimate of $352 million to implement its preferred option does not include costs such as an additional $47 million for terminating personnel. Moreover, other costs related to decontaminating and decommissioning facilities and to transferring work that the facilities conduct for others were not included. DOE's own detailed cost estimates conducted since the NCP was released show that costs for the preferred alternative are increasing. Third, the NCP did not fully address the technical risks of nonnuclear consolidation. The NCP assumed that the technical risk of moving each nonnuclear activity was the same. No additional weight was given in the analysis to moving those activities, such as the manufacture of neutron generators, that DOE acknowledges pose the greatest technical risks. Furthermore, the NCP did not assess the technical risk of an accelerated consolidation schedule, particularly its impact on the production of limited-life components - those components that must be periodically replaced to keep the nuclear weapons operational. Since the NCP's release in March 1992, DOE has continued to study various aspects of consolidation. Among other things, DOE is studying some additional options for consolidating nonnuclear activities, re-examining the costs in more detail, and reviewing the overall size and capabilities of the future complex. However, even with these additional studies DOE needs to do more to be assured that all reasonable options have been explored and that technical risks have been thoroughly examined

Crystal Structure of the Herpesvirus Nuclear Egress Complex Provides Insights into Inner Nuclear Membrane Remodeling

Directory of Open Access Journals (Sweden)

Tzviya Zeev-Ben-Mordehai

2015-12-01

Full Text Available Although nucleo-cytoplasmic transport is typically mediated through nuclear pore complexes, herpesvirus capsids exit the nucleus via a unique vesicular pathway. Together, the conserved herpesvirus proteins pUL31 and pUL34 form the heterodimeric nuclear egress complex (NEC, which, in turn, mediates the formation of tight-fitting membrane vesicles around capsids at the inner nuclear membrane. Here, we present the crystal structure of the pseudorabies virus NEC. The structure revealed that a zinc finger motif in pUL31 and an extensive interaction network between the two proteins stabilize the complex. Comprehensive mutational analyses, characterized both in situ and in vitro, indicated that the interaction network is not redundant but rather complementary. Fitting of the NEC crystal structure into the recently determined cryoEM-derived hexagonal lattice, formed in situ by pUL31 and pUL34, provided details on the molecular basis of NEC coat formation and inner nuclear membrane remodeling.

Nuclear Fuel Complex - a landmark of indigenous nuclear technology

Energy Technology Data Exchange (ETDEWEB)

Katiyar, H C [Nuclear Fuel Complex, Hyderabad (India)

1977-01-01

The Nuclear Fuel Complex (NFC) set up in India for manufacturing fuel and related hardware has proved to be a significant step towards self-sufficiency and saving of foreign exchange. The complex is involved in the entire operations starting from processing of raw material concentrates to finishing of fuel assemblies and other zircaloy reactor components. The complex consists of the following units : (1) Zirconium Oxide Plant, (2) Zirconium Sponge Plant, (3) Zircaloy Fabrication Plant, (4) Uranium Oxide Plant, (5) Ceramic Fabrication Plant, (6) Enriched Uranium Oxide Plant, (7) Enriched Fuel Fabrication Plant, (8) Special Materials Plant and (9) Titanium Plant. A brief description of the activities of the various units of the complex are given. The effluent management scheme is outlined. The requirements and cost of fuel and zircaloy components for the power stations at Tarapur, Kota and Kalpakkam are mentioned.

Logistics of nuclear fuel production for nuclear submarines

International Nuclear Information System (INIS)

Guimaraes, Leonam dos Santos

2000-01-01

The future acquisition of nuclear attack submarines by Brazilian Navy along next century will imply new requirements on Naval Logistic Support System. These needs will impact all the six logistic functions. Among them, fuel supply could be considered as the one which requires the most important capacitating effort, including not only technological development of processes but also the development of a national industrial basis for effective production of nuclear fuel. This paper presents the technical aspects of the processes involved and an annual production dimensioning for an squadron composed by four units. (author)

Medical application of nuclear science: nuclear medicine and production of radiopharmaceuticals

International Nuclear Information System (INIS)

Cornet, L.

1997-01-01

Nuclear science in attendance on medicine or from Radium to Radiopharmaceuticals. By a brief historical reminder of the evolution of the radioactivity and development of nuclear science, we could see a very early interest and application of the radioactivity in the medical field. Main steps: Detection of natural radioactivity/Discovery of artificial radioactivity/First treatment of leukaemia and thyroid/First nuclear reactor/First radioisotope laboratory in hospital/First scintigraphy/First radiopharmaceutical/First cyclotron and cyclotron products/First immunoscintigraphy/Biotechnology and radioisotope/Evolution of technics [equipment for diagnosis (imaging, scintigraphy) and therapy]/Evolution of production technics and concept of products (generators of Technetium) and machines, reactor, cyclotron/Evolution of importance and interest of nuclear medicine/Creation of international association of nuclear medicine and producers (example ARPR)/Evolution of safety and pharmaceuticals regulation. After the sixties, period extremely rich in invention of products, characterized by a high fertility specially due to a non-restrictive regulation in terms of safety and pharmaceutical consideration, the evolution of technics, the importance of costs (investment, research, healthcare and the evolution of the regulations) have smoothly but continuously transformed the contexts and different actors. Consequences and facts: Rationalization and standardization of the catalogues, total integration of radiopharmaceuticals into the pharmaceutical laws, stop of nuclear research reactors, increase of number of cyclotrons, transformation of size and role of the producers and nuclear centers, risk in supply of some raw materials like Molybdenum, medical nuclear application as a worldwide business

Dynamic Complexity Study of Nuclear Reactor and Process Heat Application Integration

Energy Technology Data Exchange (ETDEWEB)

J' Tia Patrice Taylor; David E. Shropshire

2009-09-01

Abstract This paper describes the key obstacles and challenges facing the integration of nuclear reactors with process heat applications as they relate to dynamic issues. The paper also presents capabilities of current modeling and analysis tools available to investigate these issues. A pragmatic approach to an analysis is developed with the ultimate objective of improving the viability of nuclear energy as a heat source for process industries. The extension of nuclear energy to process heat industries would improve energy security and aid in reduction of carbon emissions by reducing demands for foreign derived fossil fuels. The paper begins with an overview of nuclear reactors and process application for potential use in an integrated system. Reactors are evaluated against specific characteristics that determine their compatibility with process applications such as heat outlet temperature. The reactor system categories include light water, heavy water, small to medium, near term high-temperature, and far term high temperature reactors. Low temperature process systems include desalination, district heating, and tar sands and shale oil recovery. High temperature processes that support hydrogen production include steam reforming, steam cracking, hydrogen production by electrolysis, and far-term applications such as the sulfur iodine chemical process and high-temperature electrolysis. A simple static matching between complementary systems is performed; however, to gain a true appreciation for system integration complexity, time dependent dynamic analysis is required. The paper identifies critical issues arising from dynamic complexity associated with integration of systems. Operational issues include scheduling conflicts and resource allocation for heat and electricity. Additionally, economic and safety considerations that could impact the successful integration of these systems are considered. Economic issues include the cost differential arising due to an integrated

Elastic Network Model of a Nuclear Transport Complex

Science.gov (United States)

Ryan, Patrick; Liu, Wing K.; Lee, Dockjin; Seo, Sangjae; Kim, Young-Jin; Kim, Moon K.

2010-05-01

The structure of Kap95p was obtained from the Protein Data Bank (www.pdb.org) and analyzed RanGTP plays an important role in both nuclear protein import and export cycles. In the nucleus, RanGTP releases macromolecular cargoes from importins and conversely facilitates cargo binding to exportins. Although the crystal structure of the nuclear import complex formed by importin Kap95p and RanGTP was recently identified, its molecular mechanism still remains unclear. To understand the relationship between structure and function of a nuclear transport complex, a structure-based mechanical model of Kap95p:RanGTP complex is introduced. In this model, a protein structure is simply modeled as an elastic network in which a set of coarse-grained point masses are connected by linear springs representing biochemical interactions at atomic level. Harmonic normal mode analysis (NMA) and anharmonic elastic network interpolation (ENI) are performed to predict the modes of vibrations and a feasible pathway between locked and unlocked conformations of Kap95p, respectively. Simulation results imply that the binding of RanGTP to Kap95p induces the release of the cargo in the nucleus as well as prevents any new cargo from attaching to the Kap95p:RanGTP complex.

Productivity studies of the nuclear waste programme

International Nuclear Information System (INIS)

Lundberg, Haakan

2002-08-01

The Swedish Nuclear Inspectorate reviews and supplements the SKB proposal for cost estimations for the nuclear waste programme. These estimations are of great importance for the determination of annual fees to the Nuclear Waste Fund and guarantee amounts in accordance with the Financing Act. The majority of the Nuclear Waste Fund's assets are invested in real interest bonds, issued by the Swedish state. The average duration for the Nuclear Waste Fund investments was 12.8 years at the end of December 2001. From July 1, 2002 on the Nuclear waste Fund investments will consist of nominal and real bonds on the official market. The Fund is increased in line with the Consumer Price Index (KPI). If real costs within the nuclear waste programme increase at a faster rate than the KPI, there is a risk that the Nuclear Waste Fund will be 'under balanced'. SKI has developed a weighted index, the KBS-3-index, to compare the SKB cost re-estimate with. Productivity changes have however no impact on these indices. The KBS-3-index indicates that there might be a risk that the de facto, cost increases will exceed KPI. An improved productivity might however balance the cost escalations. Productivity is normally defined as production divided by the input of production factors. The production can be a quantity measurement or the value added. A common approach is calculation of the labour productivity. The productivity development within different industries in Sweden and in EU varies, and is not only positive. The so called DEA method is used for productivity and efficiency measurements in public and private operations. Efficiency evaluations based on known norms are not made with the DEA models. Instead the evaluation is performed in relation to an empirically based reference technology, a relative efficiency. A selection or an optimisation of output is difficult for the nuclear waste programme. It is not possible to change parts of the nuclear waste programme to something else

Failures of knowledge production in nuclear power risk management

International Nuclear Information System (INIS)

Sanne, Johan M.

2008-09-01

Risks are ascribed in processes of knowledge production, where risk objects are defined and measures taken. This knowledge is also the basis for regulatory action. Thus, uncertainties in knowledge production, based upon choices of assumptions, methods, calculations and evidence criteria for reliable data create vulnerabilities for risk management and risk regulation. A recent incident in Swedish nuclear power plant provides an opportunity to develop theories of knowledge production in complex organizations. Knowledge modes within nuclear power can be characterized as either calculated logics where evidence claims need numbers, real time logics based upon subtle signals and tacit knowledge or as policy logics, navigating between internal and external demands for safety, trustworthiness and profit. The plant had neither foreseen the triggering event nor designed the plant to withstand it. I analyze how the plant and the regulator have interpreted the event, its significance and the measures taken to prevent similar events. I also discuss alternative interpretations, lack of knowledge and the generic deficiencies in knowledge production that the event indicates. First, the plant was not as robustly designed as expected. Deficiencies in diversification may have been caused by overconfidence in the reliability of its design. Second, inadequate design was ascribed to various deficient knowledge production processes: original design of the plant, reconstruction or caused by inadequate learning from previous events. The failures in knowledge production were probably caused by insufficient integration of different knowledge processes and limitations in engineering analysis. Knowledge about risks from nuclear power operations is mainly based upon calculations and simulations, not upon real events. But knowledge and design could be improved also without accidents. Control room operators and maintenance staff can provide invaluable knowledge and methods; to improve causal

Failures of knowledge production in nuclear power risk management

Energy Technology Data Exchange (ETDEWEB)

Sanne, Johan M.

2008-09-15

Risks are ascribed in processes of knowledge production, where risk objects are defined and measures taken. This knowledge is also the basis for regulatory action. Thus, uncertainties in knowledge production, based upon choices of assumptions, methods, calculations and evidence criteria for reliable data create vulnerabilities for risk management and risk regulation. A recent incident in Swedish nuclear power plant provides an opportunity to develop theories of knowledge production in complex organizations. Knowledge modes within nuclear power can be characterized as either calculated logics where evidence claims need numbers, real time logics based upon subtle signals and tacit knowledge or as policy logics, navigating between internal and external demands for safety, trustworthiness and profit. The plant had neither foreseen the triggering event nor designed the plant to withstand it. I analyze how the plant and the regulator have interpreted the event, its significance and the measures taken to prevent similar events. I also discuss alternative interpretations, lack of knowledge and the generic deficiencies in knowledge production that the event indicates. First, the plant was not as robustly designed as expected. Deficiencies in diversification may have been caused by overconfidence in the reliability of its design. Second, inadequate design was ascribed to various deficient knowledge production processes: original design of the plant, reconstruction or caused by inadequate learning from previous events. The failures in knowledge production were probably caused by insufficient integration of different knowledge processes and limitations in engineering analysis. Knowledge about risks from nuclear power operations is mainly based upon calculations and simulations, not upon real events. But knowledge and design could be improved also without accidents. Control room operators and maintenance staff can provide invaluable knowledge and methods; to improve causal

Power technology complex for production of motor fuel from brown coals with power supply from NPPs

International Nuclear Information System (INIS)

Troyanov, M.F.; Poplavskij, V.M.; Sidorov, G.I.; Bondarenko, A.V.; Chebeskov, A.N.; Chushkin, V.N.; Karabash, A.A.; Krichko, A.A.; Maloletnev, A.S.

1998-01-01

With the present-day challenge of efficient use of low-grade coals and current restructuring of coal industry in the Russian Federation, it is urgent to organise the motor fuel production by the synthesis from low grade coals and heavy petroleum residues. With this objective in view, the Institute of Physics and Power Engineering of RF Minatom and Combustible Resources Institute of RF Mintopenergo proposed a project of a standard nuclear power technology complex for synthetic liquid fuel (SLF) production using fast neutron reactors for power supply. The proposed project has two main objectives: (1) Engineering and economical optimization of the nuclear power supply for SLF production; and (2) Engineering and economical optimization of the SLF production by hydrogenisation of brown coals and heavy petroleum residues with a complex development of advanced coal chemistry. As a first approach, a scheme is proposed with the use of existing reactor cooling equipment, in particular, steam generators of BN-600, limiting the effect on safety of reactor facility operation at minimum in case of deviations and abnormalities in the operation of technological complex. The possibility to exclude additional requirements to the equipment for nuclear facility cooling was also taken into account. It was proposed to use an intermediate steam-water circuit between the secondary circuit sodium and the coolant to heat the technological equipment. The only change required for the BN-600 equipment will be the replacement of sections of intermediate steam superheaters at the section of main steam superheaters. The economic aspects of synthetic motor fuel production proposed by the joint project depend on the evaluation of integral balances: thermal power engineering, chemical technology, the development of advanced large scale coal chemistry of high profitability; utilisation of ash and precious microelements in waste-free technology; production of valuable isotopes; radical solution of

Hydrogen Production Using Nuclear Energy

Energy Technology Data Exchange (ETDEWEB)

Verfondern, K. [Research Centre Juelich (Germany)

2013-03-15

world. In recent years, the scope of the IAEA's programme has been widened to include other more promising applications such as nuclear hydrogen production and higher temperature process heat applications. The OECD Nuclear Energy Agency, Euratom and the Generation IV International Forum have also shown interest in the non-electric applications of nuclear power based on future generation advanced and innovative nuclear reactors. This report was developed under an IAEA project with the objective of providing updated, balanced and objective information on the current status of hydrogen production processes using nuclear energy. It documents the state of the art of the development of hydrogen as an energy carrier in many Member States, as well as its corresponding production through the use of nuclear power. The report includes an introduction to the technology of nuclear process heat reactors as a means of producing hydrogen or other upgraded fuels, with a focus on high temperature reactor technology to achieve simultaneous generation of electricity and high temperature process heat and steam. Special emphasis is placed on the safety aspects of nuclear hydrogen production systems.

Progress in fission product nuclear data

International Nuclear Information System (INIS)

Lammer, M.

1981-06-01

This is the seventh issue of a report series on Fission Product Nuclear Data (FPND) which is published by the Nuclear Data Section (NDS) of the International Atomic Energy Agency (IAEA). The purpose of this series is to inform scientists working on FPND, or using such data, about all activities in this field which are planned, ongoing, or have recently been completed. The present issue contains also a section with some recent references relative to fission product nuclear data, which were not covered by the contributions submitted. The types of activities being included in this report are measurements, compilations and evaluations of: fission product yields (neutron induced and spontaneous fission); neutron reaction cross sections of fission products; data related to the radioactive decay of fission products; delayed neutron data of fission products; and lumped fission product data (decay heat, absorption etc.). The sixth issue of this series has been published in June 1980 as INDC(NDS)-113/G+P. The present issue includes contributions which were received by NDS between 1 August 1980 and 25 May 1981

Nuclear localization of Schizosaccharomyces pombe Mcm2/Cdc19p requires MCM complex assembly.

Science.gov (United States)

Pasion, S G; Forsburg, S L

1999-12-01

The minichromosome maintenance (MCM) proteins MCM2-MCM7 are conserved eukaryotic replication factors that assemble in a heterohexameric complex. In fission yeast, these proteins are nuclear throughout the cell cycle. In studying the mechanism that regulates assembly of the MCM complex, we analyzed the cis and trans elements required for nuclear localization of a single subunit, Mcm2p. Mutation of any single mcm gene leads to redistribution of wild-type MCM subunits to the cytoplasm, and this redistribution depends on an active nuclear export system. We identified the nuclear localization signal sequences of Mcm2p and showed that these are required for nuclear targeting of other MCM subunits. In turn, Mcm2p must associate with other MCM proteins for its proper localization; nuclear localization of MCM proteins thus requires assembly of MCM proteins in a complex. We suggest that coupling complex assembly to nuclear targeting and retention ensures that only intact heterohexameric MCM complexes remain nuclear.

The history of decisions on creation of nuclear and metallurgical complex on the basis of the Kola nuclear power plant

Directory of Open Access Journals (Sweden)

Kudrin B. I.

2017-02-01

Full Text Available Some reasons for the choice of directions for using electric and thermal energy of the Kola nuclear power plant located beyond the Arctic Circle have been presented. The regions of the country and their large-scale industrial productions based on metallurgical enterprises have been indicated; the electrical supply of these enterprises is implemented from the Kola NPP. The results of research of energy inputs for the production of a ton of steel and cast iron have been presented. It has been determined that the main direction of technological modernization in the steel industry is avoiding the use of organic fuels (particularly in coke-blast furnace production as the most energy-intensive and its replacement with the technology of direct reduction of iron with hydrogen. As an alternative energy source for organic fuels the creation of a fuel-free nuclear-metallurgical electrified complex has been proposed. The principal scheme of the fuel-free nuclear-metallurgical electrified complex has been described, here the main novelty has a reducing gases preparation block giving the potential ability for creating waste-free process. It has been noted that this technology requires using high temperatures and solving technical problems related to heat resistance of constructions. Some examples of world research on the implementation of similar projects have been presented. It has been determined that the use of new technology will cause the need for optimization of power consumption structure due to the redistribution of capacity and electrical consumption between productions. The introduction of new technologies requires solving a number of problems on electric power supply and electrical equipment designing. It has been observed that on the Kola NPP large-scale reconstruction was carried out during the working period, it helped to increase its project capacity and extend the operation life. Nowadays the region has excess installed capacity that can be

Hydrocarbon production with nuclear explosives

International Nuclear Information System (INIS)

Wade Watkins, J.

1970-01-01

The tremendous energy of nuclear explosives and the small dimensions of the explosive package make an ideal combination for drill-hole explosive emplacement in deep, thick hydrocarbon deposits. Potential applications exist in fracturing low permeability natural-gas and petroleum formations for stimulating production, fracturing oil shale to permit in situ retorting, and creating storage chimneys for natural gas, liquefied petroleum gas, petroleum, petroleum products, helium, and other fluids. Calculations show, for example, that less than 100 shots per year would be needed to stabilize the natural gas reserves to production ratio. Under the Government-industry Plowshare program, two experiments, Projects Gasbuggy and Rulison, were conducted to stimulate natural gas production from low-permeability formations. Incomplete information indicates that both were technically successful. Potential problems associated with the use of nuclear explosives for underground engineering applications are radioactive contamination, maximum yield limitations, high costs of detonating contained nuclear explosives, and adverse public opinion. Results at Project Gasbuggy and other considerations indicated that the problem of radioactive contamination was about as predicted and not an insurmountable one. Also, it was demonstrated that shots at adequate depths could be detonated without appreciable damage to existing surface and subsurface buildings, natural features, and equipment. However, costs must be reduced and the public must be better informed before these techniques can be widely used in field operations. On the basis of present knowledge, the potential of nuclear-explosive stimulation of hydrocarbon production appears good. Additional field experiments will be required to adequately explore that potential. (author)

Hydrocarbon production with nuclear explosives

Energy Technology Data Exchange (ETDEWEB)

Wade Watkins, J [Petroleum Research, Bureau of Mines, U.S. Department of the Interior, Washington, DC (United States)

1970-05-01

The tremendous energy of nuclear explosives and the small dimensions of the explosive package make an ideal combination for drill-hole explosive emplacement in deep, thick hydrocarbon deposits. Potential applications exist in fracturing low permeability natural-gas and petroleum formations for stimulating production, fracturing oil shale to permit in situ retorting, and creating storage chimneys for natural gas, liquefied petroleum gas, petroleum, petroleum products, helium, and other fluids. Calculations show, for example, that less than 100 shots per year would be needed to stabilize the natural gas reserves to production ratio. Under the Government-industry Plowshare program, two experiments, Projects Gasbuggy and Rulison, were conducted to stimulate natural gas production from low-permeability formations. Incomplete information indicates that both were technically successful. Potential problems associated with the use of nuclear explosives for underground engineering applications are radioactive contamination, maximum yield limitations, high costs of detonating contained nuclear explosives, and adverse public opinion. Results at Project Gasbuggy and other considerations indicated that the problem of radioactive contamination was about as predicted and not an insurmountable one. Also, it was demonstrated that shots at adequate depths could be detonated without appreciable damage to existing surface and subsurface buildings, natural features, and equipment. However, costs must be reduced and the public must be better informed before these techniques can be widely used in field operations. On the basis of present knowledge, the potential of nuclear-explosive stimulation of hydrocarbon production appears good. Additional field experiments will be required to adequately explore that potential. (author)

Micro-structured nuclear fuel and novel nuclear reactor concepts for advanced power production

International Nuclear Information System (INIS)

Popa-Simil, Liviu

2008-01-01

Many applications (e.g. terrestrial and space electric power production, naval, underwater and railroad propulsion and auxiliary power for isolated regions) require a compact-high-power electricity source. The development of such a reactor structure necessitates a deeper understanding of fission energy transport and materials behavior in radiation dominated structures. One solution to reduce the greenhouse-gas emissions and delay the catastrophic events' occurrences may be the development of massive nuclear power. The actual basic conceptions in nuclear reactors are at the base of the bottleneck in enhancements. The current nuclear reactors look like high security prisons applied to fission products. The micro-bead heterogeneous fuel mesh gives the fission products the possibility to acquire stable conditions outside the hot zones without spilling, in exchange for advantages - possibility of enhancing the nuclear technology for power production. There is a possibility to accommodate the materials and structures with the phenomenon of interest, the high temperature fission products free fuel with near perfect burning. This feature is important to the future of nuclear power development in order to avoid the nuclear fuel peak, and high price increase due to the immobilization of the fuel in the waste fuel nuclear reactor pools. (author)

USA program on the waste disposal of nuclear military complexes

International Nuclear Information System (INIS)

Vinogradova, I.

1992-01-01

The USA program on the nuclear military complex waste disposal which focuses on the problems of environment protection and recovery is briefly considered. A group of works on the updating of the existing and on the construction of new nuclear weapon undustries is chosen to be the priority direction. The problem of radioactive waste burial in the Hunford nuclear complex is discussed. Total expenses for military enterprise purification from radioactive wastes are estimated as 91.2-129 billion dollars, and expenses for realization of the whole program are estimated as 180 billion dollars for 50 years

Use of nuclear energy for hydrogen production

International Nuclear Information System (INIS)

Axente, Damian

2006-01-01

Full text: The potentials of three hydrogen production processes under development for the industrial production of hydrogen using nuclear energy, namely the advanced electrolysis the steam reforming, the sulfur-iodine water splitting cycle, are compared and evaluated in this paper. Water electrolysis and steam reforming of methane are proven and used extensively today for the production of hydrogen. The overall thermal efficiency of the electrolysis includes the efficiency of the electrical power generation and of the electrolysis itself. The electrolysis process efficiency is about 75 % and of electrical power generation is only about 30 %, the overall thermal efficiency for H 2 generation being about 25 %. Steam reforming process consists of reacting methane (or natural gas) and steam in a chemical reactor at 800-900 deg. C, with a thermal efficiency of about 70 %. In a reforming process, with heat supplied by nuclear reactor, the heat must be supplied by a secondary loop from the nuclear side and be transferred to the methane/steam mixture, via a heat exchanger type reactor. The sulfur-iodine cycle, a thermochemical water splitting, is of particular interest because it produces hydrogen efficiently with no CO 2 as byproduct. If heated with a nuclear source it could prove to be an ideal environmental solution to hydrogen production. Steam reforming remains the cheapest hydrogen production method based on the latest estimates, even when implemented with nuclear reactor. The S-I cycle offers a close second solution and the electrolysis is the most expensive of the options for industrial H 2 production. The nuclear plant could power electrolysis operations right away; steam reforming with nuclear power is a little bit further off into the future, the first operation with nuclear facility is expected to have place in Japan in 2008. The S-I cycle implementation is still over the horizon, it will be more than 10 years until we will see that cycle in full scale

Progress in fission product nuclear data

International Nuclear Information System (INIS)

Lammer, M.

1983-08-01

This is the ninth issue of a report series on Fission Product Nuclear Data (FPND) which is published by the Nuclear Data Section (NDS) of the International Atomic Energy Agency (IAEA). The purpose of this series is to inform scientists working on FPND, or using such data, about all activities in this field which are planned, ongoing, or have recently been completed. The main part of this report consists of unaltered original contributions which the authors have sent to IAEA/NDS. The present issue contains also a section with some recent references relative to fission product nuclear data, which were not covered by the contributions submitted. The types of activities being included in this report are measurements, compilations and evaluations of: Fission product yields (neutron induced and spontaneous fission); Neutron reaction cross sections of fission products; Data related to the radioactive decay of fission products; Delayed neutron data of fission products; and lumped fission product data (decay heat, absorption etc.). The eighth issue of this series has been published in July 1982 as INDC(NDS)-130. The present issue includes contributions which were received by NDS between 1 August 1982 and 25 June 1983

Nuclear envelopathies: a complex LINC between nuclear envelope and pathology.

Science.gov (United States)

Janin, Alexandre; Bauer, Delphine; Ratti, Francesca; Millat, Gilles; Méjat, Alexandre

2017-08-30

Since the identification of the first disease causing mutation in the gene coding for emerin, a transmembrane protein of the inner nuclear membrane, hundreds of mutations and variants have been found in genes encoding for nuclear envelope components. These proteins can be part of the inner nuclear membrane (INM), such as emerin or SUN proteins, outer nuclear membrane (ONM), such as Nesprins, or the nuclear lamina, such as lamins A and C. However, they physically interact with each other to insure the nuclear envelope integrity and mediate the interactions of the nuclear envelope with both the genome, on the inner side, and the cytoskeleton, on the outer side. The core of this complex, called LINC (LInker of Nucleoskeleton to Cytoskeleton) is composed of KASH and SUN homology domain proteins. SUN proteins are INM proteins which interact with lamins by their N-terminal domain and with the KASH domain of nesprins located in the ONM by their C-terminal domain.Although most of these proteins are ubiquitously expressed, their mutations have been associated with a large number of clinically unrelated pathologies affecting specific tissues. Moreover, variants in SUN proteins have been found to modulate the severity of diseases induced by mutations in other LINC components or interactors. For these reasons, the diagnosis and the identification of the molecular explanation of "nuclear envelopathies" is currently challenging.The aim of this review is to summarize the human diseases caused by mutations in genes coding for INM proteins, nuclear lamina, and ONM proteins, and to discuss their potential physiopathological mechanisms that could explain the large spectrum of observed symptoms.

Improving animal productivity by nuclear techniques

International Nuclear Information System (INIS)

Garcia, M.; Jayasuriya, M.C.N.; Perera, B.M.A.O.

1995-01-01

The IAEA and FAO have run a joint programme for 30 years to assist national agricultural research systems in member states to develop, test and apply nuclear and related techniques for improving the productivity of livestock. Applications of nuclear technologies for improving livestock productivity include: use of radioimmunoassay in animal nutrition researches, animal production, and evaluating feeding and management systems through reproductive performance in a field. Geographic coverage and the type of livestock studies are: grazing animals (cattle, goats and sheep) in Africa, Latin America and Asia, as well as buffalo production in Asia. 6 refs, 8 figs, 6 tabs

Nuclear energy for sustainable Hydrogen production

International Nuclear Information System (INIS)

Gyoshev, G.

2004-01-01

There is general agreement that hydrogen as an universal energy carrier could play increasingly important role in energy future as part of a set of solutions to a variety of energy and environmental problems. Given its abundant nature, hydrogen has been an important raw material in the organic chemical industry. At recent years strong competition has emerged between nations as diverse as the U.S., Japan, Germany, China and Iceland in the race to commercialize hydrogen energy vehicles in the beginning of 21st Century. Any form of energy - fossil, renewable or nuclear - can be used to generate hydrogen. The hydrogen production by nuclear electricity is considered as a sustainable method. By our presentation we are trying to evaluate possibilities for sustainable hydrogen production by nuclear energy at near, medium and long term on EC strategic documents basis. The main EC documents enter water electrolysis by nuclear electricity as only sustainable technology for hydrogen production in early stage of hydrogen economy. In long term as sustainable method is considered the splitting of water by thermochemical technology using heat from high temperature reactors too. We consider that at medium stage of hydrogen economy it is possible to optimize the sustainable hydrogen production by high temperature and high pressure water electrolysis by using a nuclear-solar energy system. (author)

Preliminary Cost Estimates for Nuclear Hydrogen Production: HTSE System

International Nuclear Information System (INIS)

Yang, K. J.; Lee, K. Y.; Lee, T. H.

2008-01-01

KAERI is now focusing on the research and development of the key technologies required for the design and realization of a nuclear hydrogen production system. As a preliminary study of cost estimates for nuclear hydrogen systems, the hydrogen production costs of the nuclear energy sources benchmarking GTMHR and PBMR are estimated in the necessary input data on a Korean specific basis. G4-ECONS was appropriately modified to calculate the cost for hydrogen production of HTSE (High Temperature Steam Electrolysis) process with VHTR (Very High Temperature nuclear Reactor) as a thermal energy source. The estimated costs presented in this paper show that hydrogen production by the VHTR could be competitive with current techniques of hydrogen production from fossil fuels if CO 2 capture and sequestration is required. Nuclear production of hydrogen would allow large-scale production of hydrogen at economic prices while avoiding the release of CO 2 . Nuclear production of hydrogen could thus become the enabling technology for the hydrogen economy. The major factors that would affect the cost of hydrogen were also discussed

Ownership and efficiency in nuclear power production

International Nuclear Information System (INIS)

Pollitt, M.G.

1995-01-01

This paper aims to contribute to the relatively small amount of academic literature on the efficiency of nuclear power production. The author draws on world-wide comparisons to illustrate the situation in the United Kingdom, where the nuclear generating capacity, conceived of and constructed as a public concern, has recently been privatised. The theory and evidence for links between ownership and productive efficiency is received. Efficiency measures used are explained as are the linear programs required to generate them. Data Envelopment Analysis (DEA) is used to analyse productive efficiency of nuclear power plants before and after privatisation. Results of the DEA are used to test the hypothesis that ownership has no effect on productive efficiency. (UK)

Progress in fission product nuclear data

International Nuclear Information System (INIS)

Lammer, G.

1975-01-01

This is the first issue of a report series on Fission Product Nuclear Data (FPND), published every six months by the Nuclear Data Section (NDS) of the International Atomic Energy Agency (IAEA). Its purpose is to inform scientists working on FPND, or using such data, about all activities in this field which are planned, ongoing, or have recently been completed. The types of activities being included in this report are measurements, compilations and evaluations of: fission product yields; neutron cross-section data of fission products; data related to β-, γ-decay of fission products; delayed neutron data; and fission product decay-heat. The present issue includes contributions which were received by NDS before 1 November 1975

A rhodium(III) complex inhibits LPS-induced nitric oxide production and angiogenic activity in cellulo.

Science.gov (United States)

Liu, Li-Juan; Lin, Sheng; Chan, Daniel Shiu-Hin; Vong, Chi Teng; Hoi, Pui Man; Wong, Chun-Yuen; Ma, Dik-Lung; Leung, Chung-Hang

2014-11-01

Metal-containing complexes have arisen as viable alternatives to organic molecules as therapeutic agents. Metal complexes possess a number of advantages compared to conventional carbon-based compounds, such as distinct geometries, interesting electronic properties, variable oxidation states and the ability to arrange different ligands around the metal centre in a precise fashion. Meanwhile, nitric oxide (NO) plays key roles in the regulation of angiogenesis, vascular permeability and inflammation. We herein report a novel cyclometalated rhodium(III) complex as an inhibitor of lipopolysaccharides (LPS)-induced NO production in RAW264.7 macrophages. Experiments suggested that the inhibition of NO production in cells by complex 1 was mediated through the down-regulation of nuclear factor-κB (NF-κB) activity. Furthermore, complex 1 inhibited angiogenesis in human umbilical vein endothelial cells (HUVECs) as revealed by an endothelial tube formation assay. This study demonstrates that kinetically inert rhodium(III) complexes may be potentially developed as effective anti-angiogenic agents. Copyright © 2014 Elsevier Inc. All rights reserved.

Medical Radioisotopes Production Without A Nuclear Reactor

Energy Technology Data Exchange (ETDEWEB)

Van der Keur, H.

2010-05-15

This report is answering the key question: Is it possible to ban the use of research reactors for the production of medical radioisotopes? Chapter 2 offers a summarized overview on the history of nuclear medicine. Chapter 3 gives an overview of the basic principles and understandings of nuclear medicine. The production of radioisotopes and its use in radiopharmaceuticals as a tracer for imaging particular parts of the inside of the human body (diagnosis) or as an agent in radiotherapy. Chapter 4 lists the use of popular medical radioisotopes used in nuclear imaging techniques and radiotherapy. Chapter 5 analyses reactor-based radioisotopes that can be produced by particle accelerators on commercial scale, other alternatives and the advantages of the cyclotron. Chapter 6 gives an overview of recent developments and prospects in worldwide radioisotopes production. Chapter 7 presents discussion, conclusions and recommendations, and is answering the abovementioned key question of this report: Is it possible to ban the use of a nuclear reactor for the production of radiopharmaceuticals? Is a safe and secure production of radioisotopes possible?.

Investigations of nuclear structure and nuclear reactions induced by complex projectiles

International Nuclear Information System (INIS)

Sarantites, D.G.

1991-01-01

The research program of our group touches five areas of nuclear physics: (1) Nuclear structure studies at high spin; (2) Studies at the interface between structure and reactions; (3) Production and study of hot nuclei; (4) Incomplete fusion and fragmentation reactions; and (5) Development and use of novel techniques and instrumentation in the above areas of research. The papers from these areas are discussed in this report

Systematic analysis of barrier-forming FG hydrogels from Xenopus nuclear pore complexes

NARCIS (Netherlands)

Labokha, A.A.; Gradmann, S.H.E.; Frey, S.; Hülsmann, B.B.; Urlaub, H.; Baldus, M.; Görlich, D.

2013-01-01

Nuclear pore complexes (NPCs) control the traffic between cell nucleus and cytoplasm. While facilitating translocation of nuclear transport receptors (NTRs) and NTR·cargo complexes, they suppress passive passage of macromolecules ⩾30 kDa. Previously, we reconstituted the NPC barrier as hydrogels

Nuclear Materials Characterization in the Materials and Fuels Complex Analytical Hot Cells

International Nuclear Information System (INIS)

Rodriquez, Michael

2009-01-01

As energy prices skyrocket and interest in alternative, clean energy sources builds, interest in nuclear energy has increased. This increased interest in nuclear energy has been termed the 'Nuclear Renaissance'. The performance of nuclear fuels, fuels and reactor materials and waste products are becoming a more important issue as the potential for designing new nuclear reactors is more immediate. The Idaho National Laboratory (INL) Materials and Fuels Complex (MFC) Analytical Laboratory Hot Cells (ALHC) are rising to the challenge of characterizing new reactor materials, byproducts and performance. The ALHC is a facility located near Idaho Falls, Idaho at the INL Site. It was built in 1958 as part of the former Argonne National Laboratory West Complex to support the operation of the second Experimental Breeder Reactor (EBR-II). It is part of a larger analytical laboratory structure that includes wet chemistry, instrumentation and radiochemistry laboratories. The purpose of the ALHC is to perform analytical chemistry work on highly radioactive materials. The primary work in the ALHC has traditionally been dissolution of nuclear materials so that less radioactive subsamples (aliquots) could be transferred to other sections of the laboratory for analysis. Over the last 50 years though, the capabilities within the ALHC have also become independent of other laboratory sections in a number of ways. While dissolution, digestion and subdividing samples are still a vitally important role, the ALHC has stand alone capabilities in the area of immersion density, gamma scanning and combustion gas analysis. Recent use of the ALHC for immersion density shows that extremely fine and delicate operations can be performed with the master-slave manipulators by qualified operators. Twenty milligram samples were tested for immersion density to determine the expansion of uranium dioxide after irradiation in a nuclear reactor. The data collected confirmed modeling analysis with very tight

Harnessing Product Complexity: An Integrative Approach

OpenAIRE

Orfi, Nihal Mohamed Sherif

2011-01-01

In today's market, companies are faced with pressure to increase variety in product offerings. While increasing variety can help increase market share and sales growth, the costs of doing so can be significant. Ultimately, variety causes complexity in products and processes to soar, which negatively impacts product development, quality, production scheduling, efficiency and more. Product variety is just one common cause of product complexity, a topic that several researchers have tackled with...

Plans of reorganization of USA nuclear military complex and provision of military program by special nuclear materials

International Nuclear Information System (INIS)

Semenovskaya, I.V.

1996-01-01

Consideration is given to plans and implementation of the program of reorganization of USA nuclear military complex, related with conducted reduction of nuclear arsenal after concluding the Strategic Nuclear Armament Reduction Treaty. Particular attention is paid to problems of satisfying short-term and long-term requirements in special nuclear materials and in tritium in particular

Method of investigation of nuclear reactions in charge-nonsymmetrical muonic complexes

CERN Document Server

Bystritsky, V M; Penkov, F M

1999-01-01

A method for experimental determination of the nuclear fusion rates in the d mu He molecules in the states with J=0 and J=1 (J is the orbital moment of the system) and of the effective rate of transition between these states (rotational transition 1-0) is proposed. It is shown that information on the desired characteristics can be found from joint analysis of the time distribution and yield of products of nuclear fusion reactions in deuterium-helium muonic molecules and muonic X-ray obtained in experiments with the D sub 2 +He mixture at three (and more) appreciably different densities. The planned experiments with the D sub 2 +He mixture at the meson facility PSI (Switzerland) are optimized to gain more accurate information about the desired parameters on the assumption that different mechanisms for the 1-0 transition of the d mu He complex are realized. (author)

Nuclear organization of the rock hyrax (Procavia capensis) amygdaloid complex.

Science.gov (United States)

Limacher-Burrell, Aude-Marie; Bhagwandin, Adhil; Gravett, Nadine; Maseko, Busisiwe C; Manger, Paul R

2016-07-01

The current study details the nuclear organization of the rock hyrax amygdaloid complex using both Nissl and myelin stains, along with a range of immunohistochemical stains. The rock hyrax appears to be the least derived of the Afrotherians, a group with a huge range of body phenotypes, life histories and specialized behaviours, brain sizes, and ecological niches. In this sense, the rock hyrax represents a species where the organization of the amygdaloid complex may be reflective of that in stem Eutherian mammals. Our analysis indicates that the nuclear organization of the rock hyrax amygdaloid complex is indeed very similar to that in other mammals studied, with four major nuclear groupings (the deep or basolateral group; the superficial or cortical-like or corticomedial group; the centromedial group; and the other amygdaloid nuclei) being observed, which is typical of Eutherian mammals. Moreover, each of these groupings is composed of several nuclei, the vast majority of which were readily identified in the rock hyrax. Small nuclei identified in rodents and primates were absent in the superficial and centromedial groups, seemingly involved with olfaction. A novel shell-like nucleus of the accessory basal nuclear cluster was observed in the rock hyrax, again, likely to be involved in olfaction. The current study underlines the conserved nature of nuclear parcellation in the Eutherian mammal amygdaloid complex and indicates that across most species, the flow of information processing related to species-specific affective-laden stimuli and the resultant physiological and behavioural outcomes are likely to be similar across species.

Nuclear-Renewable Energy Systems Secondary Product Market Analysis Study

Energy Technology Data Exchange (ETDEWEB)

Deason, Wesley Ray [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-06-01

In order to properly create a program surrounding the development of any technological concept it is necessary to fully understand the market in which it is being developed. In the case of Integrated Nuclear-Renewable Hybrid Energy Systems (HES), there are two economic markets in which it must be able to participate in: the electricity market and the secondary product market associated with the specific system. The purpose of the present report is to characterize the secondary product market in the U.S. and to provide recommendations for further developing the HES program. While HESs have been discussed in depth in many other reports, it is helpful to discuss them briefly in the present work [REF]. The concept of the HES can be deduced to a system, featuring a combination of a nuclear power plant, a renewable energy source, and an industrial manufacturing plant . The system is designed in a fashion that allows it either to produce electricity or to manufacture a secondary product as needed. The primary benefit of this concept lies in its ability to maximize economic performance of the integrated system and to manufacture products in a carbon-free manner. A secondary benefit is the enhanced supply-side flexibility gained by allowing the HES to economically provide grid services. A key tenant to nuclear power plant economics in today’s electricity market is their ability to operate at a very high capacity factor. Unfortunately, in regions with a high penetration of renewable energy, the carbon free energy produced by nuclear power may not be needed at all times. This forces the nuclear power plant to find a user for its excess capacity. This may include paying the electric grid to find a user, releasing energy to the environment by ‘dumping steam’, or reducing power. If the plant is unable to economically or safely do any of these actions, the plant is at risk of being shutdown. In order to allow for nuclear power plants to continue to contribute carbon free

Nuclear-Renewable Energy Systems Secondary Product Market Analysis Study

International Nuclear Information System (INIS)

Deason, Wesley Ray

2015-01-01

In order to properly create a program surrounding the development of any technological concept it is necessary to fully understand the market in which it is being developed. In the case of Integrated Nuclear-Renewable Hybrid Energy Systems (HES), there are two economic markets in which it must be able to participate in: the electricity market and the secondary product market associated with the specific system. The purpose of the present report is to characterize the secondary product market in the U.S. and to provide recommendations for further developing the HES program. While HESs have been discussed in depth in many other reports, it is helpful to discuss them briefly in the present work [REF]. The concept of the HES can be deduced to a system, featuring a combination of a nuclear power plant, a renewable energy source, and an industrial manufacturing plant . The system is designed in a fashion that allows it either to produce electricity or to manufacture a secondary product as needed. The primary benefit of this concept lies in its ability to maximize economic performance of the integrated system and to manufacture products in a carbon-free manner. A secondary benefit is the enhanced supply-side flexibility gained by allowing the HES to economically provide grid services. A key tenant to nuclear power plant economics in today's electricity market is their ability to operate at a very high capacity factor. Unfortunately, in regions with a high penetration of renewable energy, the carbon free energy produced by nuclear power may not be needed at all times. This forces the nuclear power plant to find a user for its excess capacity. This may include paying the electric grid to find a user, releasing energy to the environment by -dumping steam', or reducing power. If the plant is unable to economically or safely do any of these actions, the plant is at risk of being shutdown. In order to allow for nuclear power plants to continue to contribute carbon free

Rapid screening for nuclear genes mutations in isolated respiratory chain complex I defects.

Science.gov (United States)

Pagniez-Mammeri, Hélène; Lombes, Anne; Brivet, Michèle; Ogier-de Baulny, Hélène; Landrieu, Pierre; Legrand, Alain; Slama, Abdelhamid

2009-04-01

Complex I or reduced nicotinamide adenine dinucleotide (NADH): ubiquinone oxydoreductase deficiency is the most common cause of respiratory chain defects. Molecular bases of complex I deficiencies are rarely identified because of the dual genetic origin of this multi-enzymatic complex (nuclear DNA and mitochondrial DNA) and the lack of phenotype-genotype correlation. We used a rapid method to screen patients with isolated complex I deficiencies for nuclear genes mutations by Surveyor nuclease digestion of cDNAs. Eight complex I nuclear genes, among the most frequently mutated (NDUFS1, NDUFS2, NDUFS3, NDUFS4, NDUFS7, NDUFS8, NDUFV1 and NDUFV2), were studied in 22 cDNA fragments spanning their coding sequences in 8 patients with a biochemically proved complex I deficiency. Single nucleotide polymorphisms and missense mutations were detected in 18.7% of the cDNA fragments by Surveyor nuclease treatment. Molecular defects were detected in 3 patients. Surveyor nuclease screening is a reliable method for genotyping nuclear complex I deficiencies, easy to interpret, and limits the number of sequence reactions. Its use will enhance the possibility of prenatal diagnosis and help us for a better understanding of complex I molecular defects.

Mimicking the nuclear pore complex using nanopores

NARCIS (Netherlands)

Ananth, A.N.

2018-01-01

Nuclear pore complexes acts as a gatekeeper for molecular transport between the nucleus and the cytoplasm in eukaryotic cells. The central NPC channel is filled with intrinsically disordered FG domains (phenylalanine (F), glycine (G)) that are responsible for the fascinating selectivity of NPCs, for

Nuclear techniques in food production

International Nuclear Information System (INIS)

Merlin, J.P.C.

1975-01-01

This study is divided into three parts. The first, devoted to the use of radiations in food production, deals especially with artificial mutagenesis, selectors taking advantage of altered hereditary features in plants from irradiated seed; sterilization of animals to eliminate harmful insects (male sterilization technique); the lethal power of radiations used for the production of animal vaccins, attenuated by irradiation, against organisms which infest or degrade food products. Part two shows that radioactive atoms used as tracers to reveal migrations and chemical transformations of products such as fertilizers and pesticides can speed up all kinds of agronomical research. Their possibilities in research on animal feeding and to detect poisonous substances in foodstuffs are also mentioned. The last part is devoted to the use of nuclear techniques in irrigation and more precisely in the study of underground water flows soil moisture and lastly the future of nuclear desalination [fr

A brief review of advances in complex networks of nuclear science and technology field

International Nuclear Information System (INIS)

Fang Jinqing

2010-01-01

A brief review of advances in complex networks of nuclear science and technology field at home and is given and summarized. These complex networks include: nuclear energy weapon network, network centric warfare, beam transport networks, continuum percolation evolving network associated with nuclear reactions, global nuclear power station network, (nuclear) chemistry reaction networks, radiological monitoring and anti-nuclear terror networks, and so on. Some challenge issues and development prospects of network science are pointed out finally. (authors)

Progress in fission product nuclear data. No. 14

International Nuclear Information System (INIS)

Lammer, M.

1994-06-01

This is the 14th issue of a report series on Fission Product Nuclear Data published by the Nuclear Data Section of the IAEA. The types of activities included are measurements, compilations and evaluations of fission product yields, neutron reaction cross sections of fission products, data related to the radioactive decay of fission products, delayed neutron data from neutron induced and spontaneous fission, lumped fission product data. The first part of the report consists of unaltered original contributions which the authors have sent to IAEA/NDS. The second part contains some recent references relative to fission product nuclear data, which were not covered by the contributions submitted, and selected papers from conferences. The third part contains requirements for further measurements

An Autoimmune Myositis-Overlap Syndrome Associated With Autoantibodies to Nuclear Pore Complexes

Science.gov (United States)

Senécal, Jean-Luc; Isabelle, Catherine; Fritzler, Marvin J.; Targoff, Ira N.; Goldstein, Rose; Gagné, Michel; Raynauld, Jean-Pierre; Joyal, France; Troyanov, Yves; Dabauvalle, Marie-Christine

2014-01-01

Abstract Autoimmune myositis encompasses various myositis-overlap syndromes, each being identified by the presence of serum marker autoantibodies. We describe a novel myositis-overlap syndrome in 4 patients characterized by the presence of a unique immunologic marker, autoantibodies to nuclear pore complexes. The clinical phenotype was characterized by prominent myositis in association with erosive, anti-CCP, and rheumatoid factor-positive arthritis, trigeminal neuralgia, mild interstitial lung disease, Raynaud phenomenon, and weight loss. The myositis was typically chronic, relapsing, and refractory to corticosteroids alone, but remitted with the addition of a second immunomodulating drug. There was no clinical or laboratory evidence for liver disease. The prognosis was good with 100% long-term survival (mean follow-up 19.5 yr). By indirect immunofluorescence on HEp-2 cells, sera from all 4 patients displayed a high titer of antinuclear autoantibodies (ANA) with a distinct punctate peripheral (rim) fluorescent pattern of the nuclear envelope characteristic of nuclear pore complexes. Reactivity with nuclear pore complexes was confirmed by immunoelectron microscopy. In a cohort of 100 French Canadian patients with autoimmune myositis, the nuclear pore complex fluorescent ANA pattern was restricted to these 4 patients (4%). It was not observed in sera from 393 adult patients with systemic sclerosis (n = 112), mixed connective tissue disease (n = 35), systemic lupus (n = 94), rheumatoid arthritis (n = 45), or other rheumatic diseases (n = 107), nor was it observed in 62 normal adults. Autoantibodies to nuclear pore complexes were predominantly of IgG isotype. No other IgG autoantibody markers for defined connective tissue diseases or overlap syndromes were present, indicating a selective and highly focused immune response. In 3 patients, anti-nuclear pore complex autoantibody titers varied in parallel with myositis activity, suggesting a pathogenic

Progress in fission product nuclear data

International Nuclear Information System (INIS)

Lammer, M.

1982-07-01

This is the eighth issue of a report series on Fission Product Nuclear Data (FPND) which is published by the Nuclear Data Section (NDS) of the International Atomic Energy Agency (IAEA). The purpose of this series is to inform scientists working on FPND, or using such data, about all activities in this field which are planned, ongoing, or have recently been completed. The main part of this report consists of unaltered original contributions which the authors have sent to IAEA/NDS. Therefore, the IAEA cannot be held responsible for the information contained nor for any consequences resulting from the use of this information. The present issue contains also a section with some recent references relative to fission product nuclear data, which were not covered by the contributions submitted. The types of activities being included in this report are measurements, compilations and evaluations of: Fission product yields (neutron induced and spontaneous fission); Neutron reaction cross sections of fission products; Data related to the radioactive decay of fission products; Delayed neutron data of fission products; and lumped fission product data (decay heat, absorption etc.). The seventh issue of this series has been published in July 1981 as INDC(NDS)-116. The present issue includes contributions which were received by NDS between 1 August 1981 and 15 June 1982

Buildings 104 and 142 Complex Physical Protection and Material Control and Accounting Upgrades at the Mayak Production Association

International Nuclear Information System (INIS)

Aichele, Walter T.; Dwyer, Gregory M.; Larsen, R.; Malone, Tim

2004-01-01

The Federal State Unitary Enterprise Mayak Production Association (Mayak) and the U.S. Material Protection, Control and Accounting (MPC and A) United States Project Team (USPT) have worked together for a number of years as part of the U.S. national Nuclear Security Administration's (NNSA) MPC and A program to implement both Physical Protection (PP) and Material Control and Accounting (MC and A) upgrades within the Buildings 104 and 142 Complex, a long-term storage area for uranium and plutonium oxide located within Mayak's RT-1 Spent Fuel Reprocessing Plant. This paper focuses on the successes and areas for improvement in the analysis, planning, construction, implementation, and completion of a complex and labor-intensive project aimed at the refurbishment of two existing, in service, long-term special nuclear material (SNM) storage buildings within a Russian SNM production facility

Product development projects dynamics and emergent complexity

CERN Document Server

Schlick, Christopher

2016-01-01

This book primarily explores two topics: the representation of simultaneous, cooperative work processes in product development projects with the help of statistical models, and the assessment of their emergent complexity using a metric from theoretical physics (Effective Measure Complexity, EMC). It is intended to promote more effective management of development projects by shifting the focus from the structural complexity of the product being developed to the dynamic complexity of the development processes involved. The book is divided into four main parts, the first of which provides an introduction to vector autoregression models, periodic vector autoregression models and linear dynamical systems for modeling cooperative work in product development projects. The second part presents theoretical approaches for assessing complexity in the product development environment, while the third highlights and explains closed-form solutions for the complexity metric EMC for vector autoregression models and linear dyn...

Status of the Korean nuclear hydrogen production project

International Nuclear Information System (INIS)

Jonghwa, Chang; Won-Jae, Lee

2010-01-01

The rapid climate changes and the heavy reliance on imported fuel in Korea have motivated interest in the hydrogen economy. The Korean government has set up a long-term vision for transition to the hydrogen economy. To meet the expected demand of hydrogen as a fuel, hydrogen production using nuclear energy was also discussed. Recently the Korean Atomic Energy Committee has approved nuclear hydrogen production development and demonstration which will lead to commercialisation in late 2030's. An extensive research and development programme for the production of hydrogen using nuclear power has been underway since 2004 in Korea. During the first three years, a technological area was identified for the economic and efficient production of hydrogen using a VHTR. A pre-conceptual design of the commercial nuclear hydrogen production plant was also performed. As a result, the key technology area in the core design, the hydrogen production process, the coupling between reactor and chemical side, and the coated fuel were identified. During last three years, research activities have been focused on the key technology areas. A nuclear hydrogen production demonstration plant (NHDD) consisting of a 200 MWth capacity VHTR and five trains of water-splitting plants was proposed for demonstration of the performance and the economics of nuclear hydrogen. The computer tools for the VHTR and the water-splitting process were created and validated to some extent. The TRISO-coated particle fuel was fabricated and qualified. The properties of high temperature materials, including nuclear graphite, were studied. The sulphur-iodine thermochemical process was proved on a 3 litre/ hour scale. A small gas loop with practical pressure and temperature with the secondary sulphur acid loop was successfully built and commissioned. The results of the first phase research increased the confidence in the nuclear hydrogen technology. From 2009, the government decided to support further key technology

The CCR4-NOT complex physically and functionally interacts with TRAMP and the nuclear exosome.

Directory of Open Access Journals (Sweden)

Nowel Azzouz

Full Text Available BACKGROUND: Ccr4-Not is a highly conserved multi-protein complex consisting in yeast of 9 subunits, including Not5 and the major yeast deadenylase Ccr4. It has been connected functionally in the nucleus to transcription by RNA polymerase II and in the cytoplasm to mRNA degradation. However, there has been no evidence so far that this complex is important for RNA degradation in the nucleus. METHODOLOGY/PRINCIPAL FINDINGS: In this work we point to a new role for the Ccr4-Not complex in nuclear RNA metabolism. We determine the importance of the Ccr4-Not complex for the levels of non-coding nuclear RNAs, such as mis-processed and polyadenylated snoRNAs, whose turnover depends upon the nuclear exosome and TRAMP. Consistently, mutation of both the Ccr4-Not complex and the nuclear exosome results in synthetic slow growth phenotypes. We demonstrate physical interactions between the Ccr4-Not complex and the exosome. First, Not5 co-purifies with the exosome. Second, several exosome subunits co-purify with the Ccr4-Not complex. Third, the Ccr4-Not complex is important for the integrity of large exosome-containing complexes. Finally, we reveal a connection between the Ccr4-Not complex and TRAMP through the association of the Mtr4 helicase with the Ccr4-Not complex and the importance of specific subunits of Ccr4-Not for the association of Mtr4 with the nuclear exosome subunit Rrp6. CONCLUSIONS/SIGNIFICANCE: We propose a model in which the Ccr4-Not complex may provide a platform contributing to dynamic interactions between the nuclear exosome and its co-factor TRAMP. Our findings connect for the first time the different players involved in nuclear and cytoplasmic RNA degradation.

Nuclear weapons complex: What went wrong?

International Nuclear Information System (INIS)

Martin, J.E.

1991-01-01

The nuclear weapons complex has generated significant volumes of radioactive wastes dating back to the 1940s. Such wastes included transuranic radioisotopes-for example, plutonium-generated as byproducts of the operations. Most of these wastes at the major disposal site were not classified in the same way nuclear wastes are classified today; the definitions of high- and low-level wastes have changed over time, and, in the case of the latter, different classes have been established that determine methods for disposal and handling. Waste disposal was not a high priority during World War II. After the war, however; resources were not committed to either waste-disposal research or the development of a national waste management policy. AEC's failure to develop a national policy on radioactive waste disposal is easier to understand than to excuse. The disposal problem parallels the chemical waste disposal situation, where there were no federal and few state laws regulating chemical waste disposal until 1976, following publicity about Love Canal. This same story has been repeated for radioactive and mixed wastes and facility safety at the nation's nuclear weapon sites

Particle swarm as optimization tool in complex nuclear engineering problems

International Nuclear Information System (INIS)

Medeiros, Jose Antonio Carlos Canedo

2005-06-01

Due to its low computational cost, gradient-based search techniques associated to linear programming techniques are being used as optimization tools. These techniques, however, when applied to multimodal search spaces, can lead to local optima. When finding solutions for complex multimodal domains, random search techniques are being used with great efficacy. In this work we exploit the swarm optimization algorithm search power capacity as an optimization tool for the solution of complex high dimension and multimodal search spaces of nuclear problems. Due to its easy and natural representation of high dimension domains, the particle swarm optimization was applied with success for the solution of complex nuclear problems showing its efficacy in the search of solutions in high dimension and complex multimodal spaces. In one of these applications it enabled a natural and trivial solution in a way not obtained with other methods confirming the validity of its application. (author)

Integrating complex functions: coordination of nuclear pore complex assembly and membrane expansion of the nuclear envelope requires a family of integral membrane proteins.

Science.gov (United States)

Schneiter, Roger; Cole, Charles N

2010-01-01

The nuclear envelope harbors numerous large proteinaceous channels, the nuclear pore complexes (NPCs), through which macromolecular exchange between the cytosol and the nucleoplasm occurs. This double-membrane nuclear envelope is continuous with the endoplasmic reticulum and thus functionally connected to such diverse processes as vesicular transport, protein maturation and lipid synthesis. Recent results obtained from studies in Saccharomyces cerevisiae indicate that assembly of the nuclear pore complex is functionally dependent upon maintenance of lipid homeostasis of the ER membrane. Previous work from one of our laboratories has revealed that an integral membrane protein Apq12 is important for the assembly of functional nuclear pores. Cells lacking APQ12 are viable but cannot grow at low temperatures, have aberrant NPCs and a defect in mRNA export. Remarkably, these defects in NPC assembly can be overcome by supplementing cells with a membrane fluidizing agent, benzyl alcohol, suggesting that Apq12 impacts the flexibility of the nuclear membrane, possibly by adjusting its lipid composition when cells are shifted to a reduced temperature. Our new study now expands these findings and reveals that an essential membrane protein, Brr6, shares at least partially overlapping functions with Apq12 and is also required for assembly of functional NPCs. A third nuclear envelope membrane protein, Brl1, is related to Brr6, and is also required for NPC assembly. Because maintenance of membrane homeostasis is essential for cellular survival, the fact that these three proteins are conserved in fungi that undergo closed mitoses, but are not found in metazoans or plants, may indicate that their functions are performed by proteins unrelated at the primary sequence level to Brr6, Brl1 and Apq12 in cells that disassemble their nuclear envelopes during mitosis.

Product variety, product complexity and manufacturing operational performance: A systematic literature review

DEFF Research Database (Denmark)

Trattner, Alexandria Lee; Hvam, Lars; Herbert-Hansen, Zaza Nadja Lee

Manufacturing in the twenty-first century has been wrought with the struggle to satisfy the rising demand for greater product variety and more complex products while still maintaining efficient manufacturing operations. However, the literature lacks an overview of which operational performance...... measures are most affected by increased variety and complexity. This study presents a systematic literature review of the recent scholarly literature on variety, complexity and manufacturing operational performance (MOP). Results show that product variety has a consistently negative relationship with MOP...... across different time, cost, quality and flexibility measures while product complexity lacks evidence of strong relationships with MOP measures....

Advanced nuclear plant control complex

International Nuclear Information System (INIS)

Scarola, K.; Jamison, S.; Manazir, R.M.; Rescorl, R.L.; Harmon, D.L.

1991-01-01

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system which is nuclear qualified for rapid response to changes in plant parameters and a component control system which together provide a discrete monitoring and control capability at a panel in the control room. A separate data processing system, which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs and a large, overhead integrated process status overview board. The discrete indicator and alarm system and the data processing system receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accidental conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof. (author)

Establishing and development of nuclear power production in the Republic of Kazakhstan

International Nuclear Information System (INIS)

Kadyrzhanov, K.K.; Zhotabayev, Zh.R.

2007-01-01

Full text: As it was stressed by the President of the Republic of Kazakhstan N. Nazarbaev in his address to people of Kazakhstan on February 28 2007, among the most important directions of domestic and foreign policy there is the need in development of power production and creation of conditions for nuclear power production. Intensive development of new and revived sectors such as machine-building, oil chemistry, nuclear, space, information, nano- and bio-technologies would inevitably require growth in power generation. That is why development of power production becomes a priority task. Growth of demand in power consumption worldwide, rise in prices for oil and natural gas, toughening of environmental regulations for utilization of organic fuel, concerns regarding energy supply security in many countries stipulate growth of interest to nuclear power production. International experience in power production shows the advantages and need in development of nuclear power production. In energy production, people currently use organic fuel, hydropower and alternative energy source; current share of nuclear production in the total rate of energy generation comprises about 17%. The Republic has considerable grounds for development of nuclear power production - well-developed uranium mining and processing National Company 'KazAtomProm' and a State Enterprise 'National Nuclear Center'. Creation of nuclear power production sector and development of nuclear power production in the country would help solving a set of inter-related problems aimed to satisfaction of demand in energy production by diversification of energy supply sources. This, in turn, would contribute to effective and balanced utilization of available mineral resources, improve export capacities of the country, assure environmental security at energy production; it would also preserve and develop science and technology in the country in the field of nuclear power production and nuclear industry. Objective and

Long-lived legacy: Managing high-level and transuranic waste at the DOE Nuclear Weapons Complex. Background paper

International Nuclear Information System (INIS)

1991-05-01

The document focuses on high-level and transuranic waste at the DOE nuclear weapons complex. Reviews some of the critical areas and aspects of the DOE waste problem in order to provide data and further analysis of important issues. Partial contents, High-Level Waste Management at the DOE Weapons Complex, are as follows: High-Level Waste Management: Present and Planned; Amount and Distribution; Current and Potential Problems; Vitrification; Calcination; Alternative Waste Forms for the Idaho National Engineering Laboratory; Technologies for Pretreatment of High-Level Waste; Waste Minimization; Regulatory Framework; Definition of High-Level Waste; Repository Delays and Contingency Planning; Urgency of High-Level Tank Waste Treatment; Technologies for High-Level Waste Treatment; Rethinking the Waste Form and Package; Waste Form for the Idaho National Engineering Laboratory; Releases to the Atmosphere; Future of the PUREX Plant at Hanford; Waste Minimization; Tritium Production; International Cooperation; Scenarios for Future HLW Production. Partial contents of Chapter 2, Managing Transuranic Waste at the DOE Nuclear Weapons Complex, are as follows: Transuranic Waste at Department of Energy Sites; Amount and Distribution; Waste Management: Present and Planned; Current and Potential Problems; Three Technologies for Treating Retrievably Stored Transuranic Waste; In Situ Vitrification; The Applied Research, Development, Demonstration, Testing, and Evaluation Plan (RDDT ampersand E); Actinide Conversion (Transmutation); Waste Minimization; The Regulatory Framework; Definition of, and Standards for, Disposal of Transuranic Waste; Repository Delays; Alternative Storage and Disposal Strategies; Remediation of Buried Waste; The Waste Isolation Pilot Plant; Waste Minimization; Scenarios for Future Transuranic Waste Production; Conditions of No-Migration Determination

Chemical immobilization of fission products reactive with nuclear reactor components

International Nuclear Information System (INIS)

Grossman, L.N.; Kaznoff, A.I.; Clukey, H.V.

1975-01-01

This invention teaches a method of immobilizing deleterious fission products produced in nuclear fuel materials during nuclear fission chain reactions through the use of additives. The additives are disposed with the nuclear fuel materials in controlled quantities to form new compositions preventing attack of reactor components, especially nuclear fuel cld, by the deleterious fission products. (Patent Office Record)

Measurements of nuclear data and possibility to construct the nuclear data production facility based on electron linac

Energy Technology Data Exchange (ETDEWEB)

Namkung, Won; Ko, In Soo; Cho, Moo Hyun; Kim, Gui Nyun; Lee, Young Seok; Kang, Heung Sik [Pohang University of Science and Technology, Pohang(Korea)

2001-04-01

In order to construct an infrastructure to produce nuclear data, we studied three main items; (1) Study on the possibility to construct a facility for nuclear data production, (2) Production of nuclear data for nuclear power plant, and (3) Pulsed neutron source based on a 100-MeV electron linac at Pohang Accelerator Laboratory (PAL). We confirmed the possibility to build a nuclear data production facility utilizing a 100-MeV electron linac at PAL and manpower who wanted to participate the nuclear data production experiments. In order to measure the nuclear data for nuclear power plant, we used several nuclear data production facilities in abroad. We measured total cross sections and neutron caprure cross sections for {sup nat}Dy and {sup nat}Hf using the pulsed neutron facility in the Research Reactor Institute, Kyoto University (KURRI). The neutron capture cross sections for {sup 161,162,163,164}Dy were measured at KURRI in the neutron energy region between 0.001 eV and several tens keV, and at the fast neutron facility in Tokyo Institute of Technology in the neutron energy region between 10 keV and 100 keV. We also measured the neutron capture cross sections and gamma multiplicity of {sup 232}Th at the IBR30 in Dubna, Russia. We have construct a pulsed neutron source using a 100-MeV electron linac at PAL. We measured neutron time-of-flight (TOF) spectra in order to check the characteristics of the pulsed neutron source. We also measured a neutron total cross sections of W and Cu. The pulsed neutron facility can be utilized in the education facility for nuclear data production and the test facility for the R and D purpose of the nuclear data production facility. 29 refs., 57 figs., 22 tabs. (Author)

Hydrogen production by nuclear heat

International Nuclear Information System (INIS)

Crosbie, Leanne M.; Chapin, Douglas

2003-01-01

A major shift in the way the world obtains energy is on the horizon. For a new energy carrier to enter the market, several objectives must be met. New energy carriers must meet increasing production needs, reduce global pollution emissions, be distributed for availability worldwide, be produced and used safely, and be economically sustainable during all phases of the carrier lifecycle. Many believe that hydrogen will overtake electricity as the preferred energy carrier. Hydrogen can be burned cleanly and may be used to produce electricity via fuel cells. Its use could drastically reduce global CO 2 emissions. However, as an energy carrier, hydrogen is produced with input energy from other sources. Conventional hydrogen production methods are costly and most produce carbon dioxide, therefore, negating many of the benefits of using hydrogen. With growing concerns about global pollution, alternatives to fossil-based hydrogen production are being developed around the world. Nuclear energy offers unique benefits for near-term and economically viable production of hydrogen. Three candidate technologies, all nuclear-based, are examined. These include: advanced electrolysis of water, steam reforming of methane, and the sulfur-iodine thermochemical water-splitting cycle. The underlying technology of each process, advantages and disadvantages, current status, and production cost estimates are given. (author)

Qualified Coatings in Nuclear Power Plants. Commercial products; Qualified Coatings in Nuclear Power Plants. Commercial products. Pinturas homologadas en centrales nucleares. Productos comerciales

Energy Technology Data Exchange (ETDEWEB)

Barcena, J.; Nunez, B.; Romero, M.; Baladiam, M.

2014-07-01

Recently, the supplier of paints that were qualified for use in nuclear applications as protective coatings have ceased to supply in Spain the paints that was used in areas or components with special requirements for nuclear power plants (NPPs). This lack of the common commercial products called for the search for and homologation of other products. A study was performed on the current status of the homologation of commercial products for NPPs and on the codes and standards governing them. The criteria to be met have been defined and the results of the tests performed on the selected paints have been compared against the established criteria so as to allow the homologation of the paints. (Author)

Some political issues related to future special nuclear materials production

International Nuclear Information System (INIS)

Peaslee, A.T. Jr.

1981-08-01

The Federal Government must take action to assure the future adequate supply of special nuclear materials for nuclear weapons. Existing statutes permit the construction of advanced defense production reactors and the reprocessing of commercial spent fuel for the production of special materials. Such actions would not only benefit the US nuclear reactor manufacturers, but also the US electric utilities that use nuclear reactors

Validation of Product Properties Considering a High Variety of Complex Products

OpenAIRE

Kortler, S.;Kohn, A.;Lindemann, U.

2017-01-01

Validation processes are becoming more and more complex. Due to rising technical capabilities and a wide variety of customer requirements, OEMs are increasing their product variety in order to increase profits. According to the various characteristics of subcontracted components involved in complex products, the product variety can be very high. The impacts of the involved subcontracted components on the composed product variety during the product’s application are difficult to predict. This ...

Plant Design Nuclear Fuel Element Production Capacity Optimization to Support Nuclear Power Plant in Indonesia

International Nuclear Information System (INIS)

Bambang Galung Susanto

2007-01-01

The optimization production capacity for designing nuclear fuel element fabrication plant in Indonesia to support the nuclear power plant has been done. From calculation and by assuming that nuclear power plant to be built in Indonesia as much as 12 NPP and having capacity each 1000 MW, the optimum capacity for nuclear fuel element fabrication plant is 710 ton UO 2 /year. The optimum capacity production selected, has considered some aspects such as fraction batch (cycle, n = 3), length of cycle (18 months), discharge burn-up value (Bd) 35,000 up 50,000 MWD/ton U, enriched uranium to be used in the NPP (3.22 % to 4.51 %), future market development for fuel element, and the trend of capacity production selected by advances country to built nuclear fuel element fabrication plant type of PWR. (author)

Hydrogen production as a promising nuclear energy application

International Nuclear Information System (INIS)

Vanek, V.

2003-01-01

Hydrogen production from nuclear is a field of application which eventually can outweigh power production by nuclear power plants. There are two feasible routes of hydrogen production. The one uses heat to obtain hydrogen from natural gas through steam reforming of methane. This is an highly energy-consuming process requiring temperatures up to 900 deg C and producing carbon dioxide as a by-product. The other method includes direct thermochemical processes to obtain hydrogen, using sulfuric acid for instance. Sulfuric acid is decomposed thermally by the reaction: H 2 SO 4 -> H 2 O = SO 2 + (1/2) O 2 , followed by the processes I 2 + SO 2 + 2H O -> 2HI + H 2 SO 4 and 2HI -> H 2 + I 2 . The use of nuclear for this purpose is currently examined in Japan and in the US. (P.A.)

The Synthesis of 58co-Naphthenate Complex Compound for Evaluation of Oil well Production Capacity

International Nuclear Information System (INIS)

Duyeh Setiawan; Marlina

2009-01-01

The nuclear technique using radioisotope as a tracer in oil industry has assisted to solve the degradation of oil production. Usually, the degradation of oil production in well caused by the formation changing of hydrostatic pressure of the oil layer in the well. This problem could be evaluated by injection of water to oil well, for recovering this hydrostatic pressure. The watcher of the water injection success is done by the way of nuclear technique radioactive tracer systems, applied radioisotope having short half life and low gamma radiation energy. Radioisotope cobalt-58 in the complex form with naphthenate ( 58 Co-naphthenate ) often used as the tracer in the water injection technique. The tracer 58 Co-naphthenate relatively easy to synthesis and radioisotope 58 Co has half life 70.86 days and gamma energy was 0.811 Me v. The synthesis method of 58 Co-naphthenate route has been carried out by mixing of 58 CoCl 2 radioisotope solution with sodium naphthenate (C 5 H 9 CH 2 COONa) in the optimum condition. The results shows that the optimal mole ratio of cobalt-58 and naphthenate was 1:6 which produced 87,38 % of ren dement and 82,5 % of efficiency labelling. This synthesis technique was made permanent procedure for making of 58 Co-naphthenate complex as radioactive tracer in service of radioisotope production especially industrial area. (author)

Agriculture products as source of radionuclides and some monitoring principles of agriculture near nuclear facilities

International Nuclear Information System (INIS)

Aleksakhin, R.M.; Korneev, N.A.; Panteleev, L.I.; Shukhovtsev, B.I.

1985-01-01

Migration of radionuclides into agriculture products in regions adjoining the nuclear facilities depends on a large number of factors. Among them is the complex of ecological conditions: meteorological factors, type of soils etc., as well as biological peculiarities of agriculture plants and animals. It is possible to control the radionuclide content administered to man's organism with agriculture products changing large branches of agriculture and varying within the range of seprate branches of industry, taking into account the most effective ways of radionuclide pathways

Human Cytomegalovirus Nuclear Capsids Associate with the Core Nuclear Egress Complex and the Viral Protein Kinase pUL97.

Science.gov (United States)

Milbradt, Jens; Sonntag, Eric; Wagner, Sabrina; Strojan, Hanife; Wangen, Christina; Lenac Rovis, Tihana; Lisnic, Berislav; Jonjic, Stipan; Sticht, Heinrich; Britt, William J; Schlötzer-Schrehardt, Ursula; Marschall, Manfred

2018-01-13

The nuclear phase of herpesvirus replication is regulated through the formation of regulatory multi-component protein complexes. Viral genomic replication is followed by nuclear capsid assembly, DNA encapsidation and nuclear egress. The latter has been studied intensely pointing to the formation of a viral core nuclear egress complex (NEC) that recruits a multimeric assembly of viral and cellular factors for the reorganization of the nuclear envelope. To date, the mechanism of the association of human cytomegalovirus (HCMV) capsids with the NEC, which in turn initiates the specific steps of nuclear capsid budding, remains undefined. Here, we provide electron microscopy-based data demonstrating the association of both nuclear capsids and NEC proteins at nuclear lamina budding sites. Specifically, immunogold labelling of the core NEC constituent pUL53 and NEC-associated viral kinase pUL97 suggested an intranuclear NEC-capsid interaction. Staining patterns with phospho-specific lamin A/C antibodies are compatible with earlier postulates of targeted capsid egress at lamina-depleted areas. Important data were provided by co-immunoprecipitation and in vitro kinase analyses using lysates from HCMV-infected cells, nuclear fractions, or infectious virions. Data strongly suggest that nuclear capsids interact with pUL53 and pUL97. Combined, the findings support a refined concept of HCMV nuclear trafficking and NEC-capsid interaction.

Human Cytomegalovirus Nuclear Capsids Associate with the Core Nuclear Egress Complex and the Viral Protein Kinase pUL97

Directory of Open Access Journals (Sweden)

Jens Milbradt

2018-01-01

Full Text Available The nuclear phase of herpesvirus replication is regulated through the formation of regulatory multi-component protein complexes. Viral genomic replication is followed by nuclear capsid assembly, DNA encapsidation and nuclear egress. The latter has been studied intensely pointing to the formation of a viral core nuclear egress complex (NEC that recruits a multimeric assembly of viral and cellular factors for the reorganization of the nuclear envelope. To date, the mechanism of the association of human cytomegalovirus (HCMV capsids with the NEC, which in turn initiates the specific steps of nuclear capsid budding, remains undefined. Here, we provide electron microscopy-based data demonstrating the association of both nuclear capsids and NEC proteins at nuclear lamina budding sites. Specifically, immunogold labelling of the core NEC constituent pUL53 and NEC-associated viral kinase pUL97 suggested an intranuclear NEC-capsid interaction. Staining patterns with phospho-specific lamin A/C antibodies are compatible with earlier postulates of targeted capsid egress at lamina-depleted areas. Important data were provided by co-immunoprecipitation and in vitro kinase analyses using lysates from HCMV-infected cells, nuclear fractions, or infectious virions. Data strongly suggest that nuclear capsids interact with pUL53 and pUL97. Combined, the findings support a refined concept of HCMV nuclear trafficking and NEC-capsid interaction.

History of Nuclear Weapons Design and Production

Science.gov (United States)

Oelrich, Ivan

2007-04-01

The nuclear build-up of the United States and the Soviet Union during the Cold War is often portrayed as an arms race. Some part was indeed a bilateral competition, but much was the result of automatic application of technical advances as they became available, without careful consideration of strategic implications. Thus, the history of nuclear weapon design is partly designers responding to stated military needs and partly the world responding to constant innovations in nuclear capability. Today, plans for a new nuclear warhead are motivated primarily by the desire to maintain a nuclear design and production capability for the foreseeable future.

Kaon production in intermediate-energy nuclear collisions

International Nuclear Information System (INIS)

Russkikh, V.N.; Ivanov, Yu.B.

1992-01-01

Production of positive kaons in nuclear collisions at intermediate energies (∝ 1-2 GeV/nucleon) is studied within the 3-dimensional fluid dynamics combined with the hadrochemical kinetics for strangeness production. Sensitivity of the kaon probe to a form of the nuclear equation of state is analyzed. The model reproduces total and differential cross sections of Ne+NaF→K + +X and Ne+Pb→K + +X reactions at E lab =2.1 GeV/nucleon, provided a soft equation of state is used. The pion-production data are also well described employing the same equation of state. Predictions are made for the current experiment on kaon production at the SIS accelerator. The obtained results are compared with the predictions of other models. (orig.)

Progress in fission product nuclear data

International Nuclear Information System (INIS)

Lammer, M.

1984-09-01

This is the tenth issue of a report series on Fission Product Data, which informs us about all the activities in this field, which are planned, ongoing, or have recently been completed. The types of activities included are measurements, compilations and evaluations of: fission product yields (neutron induced and spontaneous fission), neutron reaction cross sections of fission products, data related to the radioactive decay of fission products, delayed neutron data of fission products, lumped fission product data (decay heat, absorption, etc.). There is also a section with recent references relative to fission product nuclear data

The Y-12 National Security Complex Foreign Research Reactor Uranium Supply Production

Energy Technology Data Exchange (ETDEWEB)

Nelson, T. [Nuclear Technology and Nonproliferation Programs, B and W Y-12, L.L.C., Y-12 National Security Complex, Oak Ridge, Tennessee (United States); Keller, A.P. [Disposition and Supply Programs, B and W Y-12, L.L.C., Y-12 National Security Complex, Oak Ridge, Tennessee (United States)

2011-07-01

The Foreign Research Reactor (FRR) Uranium Supply Program at the Y-12 National Security Complex supports the nonproliferation objectives of the National Nuclear Security Administration (NNSA) HEU Disposition, the Reduced Enrichment Research and Test Reactors (RERTR), and the United States (U.S.) FRR Spent Nuclear Fuel (SNF) Acceptance Programs. The FRR Supply Program supports the important U.S. government nuclear nonproliferation commitment to serve as a reliable and cost-effective uranium supplier for those foreign research reactors that are converting or have converted to Low-Enriched Uranium (LEU) fuel under the RERTR Program. The NNSA Y-12 Site Office maintains the prime contracts with foreign government agencies for the supply of LEU for their research reactors. The LEU is produced by down blending Highly Enriched Uranium (HEU) that has been declared surplus to the U.S. national defense needs. The down blending and sale of the LEU supports the Surplus HEU Disposition Program Record of Decision to make the HEU non-weapons usable and to recover the economic value of the uranium to the extent feasible. In addition to uranium metal feedstock for fuel fabrication, Y-12 can produce LEU in different forms to support new fuel development or target fabrication for medical isotope production. With production improvements and efficient delivery preparations, Y-12 continues to successfully support the global research reactor community. (author)

An Adenovirus DNA Replication Factor, but Not Incoming Genome Complexes, Targets PML Nuclear Bodies.

Science.gov (United States)

Komatsu, Tetsuro; Nagata, Kyosuke; Wodrich, Harald

2016-02-01

Promyelocytic leukemia protein nuclear bodies (PML-NBs) are subnuclear domains implicated in cellular antiviral responses. Despite the antiviral activity, several nuclear replicating DNA viruses use the domains as deposition sites for the incoming viral genomes and/or as sites for viral DNA replication, suggesting that PML-NBs are functionally relevant during early viral infection to establish productive replication. Although PML-NBs and their components have also been implicated in the adenoviral life cycle, it remains unclear whether incoming adenoviral genome complexes target PML-NBs. Here we show using immunofluorescence and live-cell imaging analyses that incoming adenovirus genome complexes neither localize at nor recruit components of PML-NBs during early phases of infection. We further show that the viral DNA binding protein (DBP), an early expressed viral gene and essential DNA replication factor, independently targets PML-NBs. We show that DBP oligomerization is required to selectively recruit the PML-NB components Sp100 and USP7. Depletion experiments suggest that the absence of one PML-NB component might not affect the recruitment of other components toward DBP oligomers. Thus, our findings suggest a model in which an adenoviral DNA replication factor, but not incoming viral genome complexes, targets and modulates PML-NBs to support a conducive state for viral DNA replication and argue against a generalized concept that PML-NBs target incoming viral genomes. The immediate fate upon nuclear delivery of genomes of incoming DNA viruses is largely unclear. Early reports suggested that incoming genomes of herpesviruses are targeted and repressed by PML-NBs immediately upon nuclear import. Genome localization and/or viral DNA replication has also been observed at PML-NBs for other DNA viruses. Thus, it was suggested that PML-NBs may immediately sense and target nuclear viral genomes and hence serve as sites for deposition of incoming viral genomes and

Evaluation of Nuclear Hydrogen Production System

International Nuclear Information System (INIS)

Park, Won Seok; Park, C. K.; Park, J. K. and others

2006-04-01

The major objective of this work is tow-fold: one is to develop a methodology to determine the best VHTR types for the nuclear hydrogen demonstration project and the other is to evaluate the various hydrogen production methods in terms of the technical feasibility and the effectiveness for the optimization of the nuclear hydrogen system. Both top-tier requirements and design requirements have been defined for the nuclear hydrogen system. For the determination of the VHTR type, a comparative study on the reference reactors, PBR and PBR, was conducted. Based on the analytic hierarchy process (AHP) method, a systematic methodology has been developed to compare the two VHTR types. Another scheme to determine the minimum reactor power was developed as well. Regarding the hydrogen production methods, comparison indices were defined and they were applied to the IS (Iodine-Sulfur) scheme, Westinghouse process, and the, high-temperature electrolysis method. For the HTE, IS, and MMI cycle, the thermal efficiency of hydrogen production were systematically evaluated. For the IS cycle, an overall process was identified and the functionality of some key components was identified. The economy of the nuclear hydrogen was evaluated, relative to various primary energy including natural gas coal, grid-electricity, and renewable. For the international collaborations, two joint research centers were established: NH-JRC between Korea and China and NH-JDC between Korea and US. Currently, several joint researches are underway through the research centers

The safe production of hydrogen by nuclear power

International Nuclear Information System (INIS)

Verfondern, Karl

2009-01-01

One of the most promising 'GEN-IV' nuclear reactor concepts is the Very High Temperature Reactor (VHTR). It is characterized by a helium-cooled, graphite moderated, thermal neutron spectrum reactor core of 400-600 MW(th). Coolant outlet temperatures of 900-1000 .deg. C ideally suited for a wide spectrum of high temperature process heat or process steam applications, which allow to deliver, besides the classical electricity, also non-electrical products such as hydrogen or other fuels. In a future energy economy, hydrogen as a storable medium could adjust a variable demand for electricity by means of fuel cell power plants providing much more flexibility in optimized energy structures. The mass production of hydrogen is a major goal for Gen-IV systems. In a nuclear hydrogen production facility, the coupling between the nuclear plant and the process heat/steam application side is given by an intermediate heat exchanger (IHX), a component which provides a clear separation preventing the primary coolant from accessing the heat application plant and, vice versa, any process gases from being routed through the reactor containment. The physical separation has the advantage that the heat application facility can be conventionally designed, and repair works can be conducted under non-nuclear conditions. With regard to the safety of combined nuclear and chemical facilities, apart from their own specific categories of hazards, a qualitatively new class of events will have to be taken into account characterized by interacting influences. Arising problems to be covered by a decent overall safety concept are the questions of safety of the nuclear plant in case of fire and explosion hazards resulting from the leakage of flammable substances, the tolerable tritium contamination of the product hydrogen, or the situations of thermo-dynamic feedback in case of a loss of heat source (nuclear) or heat sink (chemical) resulting in thermal turbulences. A safety-related issue is the

Shelf life study on Nuclear Malaysia biofertilizer products

International Nuclear Information System (INIS)

Phua Choo Kwai Hoe; Ahmad Nazrul Abd Wahid; Khairuddin Abdul Rahim

2009-01-01

Phosphate solubilising bacteria and plant growth promoting rhizobacteria are biofertilizer microorganisms known to increase crop yields. It is important to prepare suitable sterile carriers or substrates for these microorganisms into biofertilizer products with long shelf life. Optimum storage conditions, especially storage temperature is needed to improve shelf life of the products. Isolates of two phosphate solubilising bacteria (AP1 and AP3) and one plant growth promoting rhizobacteria (AP2) have been developed into biofertilizer products in Malaysian Nuclear Agency (NuclearMalaysia). These isolates were inoculated into a compost-based carrier, sterilised by gamma irradiation at 50 kGy, from MINTec-SINAGAMA, Nuclear Malaysia. Biofertilizer products kept at low temperatures (9 ± 2 degree C) showed better shelf life (storage for six months) as compared to those stored at room temperatures (28 ± 2 degree C). Further observation of the shelf life is still in progress. (Author)

Production of nuclear grade zirconium: A review

Energy Technology Data Exchange (ETDEWEB)

Xu, L., E-mail: L.Xu-2@tudelft.nl [School of Materials Science and Metallurgy, Northeastern University, Shenyang 110004 (China); Department of Materials Science and Engineering, Delft University of Technology, Delft 2628 CD (Netherlands); Xiao, Y. [Department of Metallurgical Engineering, Anhui University of Technology, Ma' anshan 243002 (China); Zr-Hf-Ti Metallurgie B.V., Den Haag 2582 SB (Netherlands); Sandwijk, A. van [Zr-Hf-Ti Metallurgie B.V., Den Haag 2582 SB (Netherlands); Xu, Q. [School of Materials Science and Metallurgy, Northeastern University, Shenyang 110004 (China); Yang, Y. [Department of Materials Science and Engineering, Delft University of Technology, Delft 2628 CD (Netherlands)

2015-11-15

Zirconium is an ideal material for nuclear reactors due to its low absorption cross-section for thermal neutrons, whereas the typically contained hafnium with strong neutron-absorption is very harmful for zirconium as a fuel cladding material. This paper provides an overview of the processes for nuclear grade zirconium production with emphasis on the methods of Zr–Hf separation. The separation processes are roughly classified into hydro- and pyrometallurgical routes. The known pyrometallurgical Zr–Hf separation methods are discussed based on the following reaction features: redox characteristics, volatility, electrochemical properties and molten salt–metal equilibrium. In the present paper, the available Zr–Hf separation technologies are compared. The advantages and disadvantages as well as future directions of research and development for nuclear grade zirconium production are discussed.

Nuclear reactor structural material forming less radioactive corrosion product

International Nuclear Information System (INIS)

Nakazawa, Hiroshi.

1988-01-01

Purpose: To provide nuclear reactor structural materials forming less radioactive corrosion products. Constitution: Ni-based alloys such as inconel alloy 718, 600 or inconel alloy 750 and 690 having excellent corrosion resistance and mechanical property even in coolants at high temperature and high pressure have generally been used as nuclear reactor structural materials. However, even such materials yield corrosion products being attacked by coolants circulating in the nuclear reactor, which produce by neutron irradiation radioactive corrosion products, that are deposited in primary circuit pipeways to constitute exposure sources. The present invention dissolves dissolves this problems by providing less activating nuclear reactor structural materials. That is, taking notice on the fact that Ni-58 contained generally by 68 % in Ni changes into Co-58 under irradiation of neutron thereby causing activation, the surface of nuclear reactor structural materials is applied with Ni plating by using Ni with a reduced content of Ni-58 isotopes. Accordingly, increase in the radiation level of the nuclear reactor structural materials can be inhibited. (K.M.)

Green technology into nuclear industry Eligibility of Ambidexter nuclear complex for a generation IV nuclear power system

International Nuclear Information System (INIS)

Park, Kwangheon; Koh, Moosung; Ryu, Jeongdong; Kim, Yangeun; Lee, Bumsik; Park, Hyuntack

2000-01-01

Green power is being developed up to a point that is feasible not only in an environmental sense, but also in an economical viewpoint. This paper introduces two case studies that applied green technology into nuclear industry. 1) Nuclear laundry: A laundry machine that uses liquid and supercritical Co 2 as a solvent for decontamination of contaminated working dresses in nuclear power plants was developed. The machine consists of a 16 liter reactor, a recovery system with compressors, and storage tanks. All CO 2 used in cleaning is fully recovered and reused in next cleaning, resulting in no production

Nuclear energy products except the electric power

International Nuclear Information System (INIS)

2004-01-01

Technically the fission reactors, on service or under construction, can produce other products than the electric power. Meanwhile, these applications are known since the beginning of the reactors exploitation, they never have been developed industrially. This report examines the necessary technical characteristics for using the nuclear systems on non electric power applications with an economical efficiency. What are the markets for these products? What are the strategical challenges to favor the development of non electric power applications of the nuclear energy? (A.L.B.)

Potential effects of nuclear war on agricultural productivity

International Nuclear Information System (INIS)

Harwell, M.A.; Cropper, W.P. Jr.

1985-01-01

The authors examine the vulnerabilities of agricultural systems to nuclear war-induced climatic perturbations and to other, indirect effects of nuclear war. Discussion is included of the dependency of agricultural production on technological inputs and the effects of loss or reduction of these inputs in a post-nuclear war world

Nuclear hydrogen: An assessment of product flexibility and market viability

International Nuclear Information System (INIS)

Botterud, Audun; Yildiz, Bilge; Conzelmann, Guenter; Petri, Mark C.

2008-01-01

Nuclear energy has the potential to play an important role in the future energy system as a large-scale source of hydrogen without greenhouse gas emissions. Thus far, economic studies of nuclear hydrogen tend to focus on the levelized cost of hydrogen without accounting for the risks and uncertainties that potential investors would face. We present a financial model based on real options theory to assess the profitability of different nuclear hydrogen production technologies in evolving electricity and hydrogen markets. The model uses Monte Carlo simulations to represent uncertainty in future hydrogen and electricity prices. It computes the expected value and the distribution of discounted profits from nuclear hydrogen production plants. Moreover, the model quantifies the value of the option to switch between hydrogen and electricity production, depending on what is more profitable to sell. We use the model to analyze the market viability of four potential nuclear hydrogen technologies and conclude that flexibility in output product is likely to add significant economic value for an investor in nuclear hydrogen. This should be taken into account in the development phase of nuclear hydrogen technologies

Application of colony complex algorithm to nuclear component optimization design

International Nuclear Information System (INIS)

Yan Changqi; Li Guijing; Wang Jianjun

2014-01-01

Complex algorithm (CA) has got popular application to the region of nuclear engineering. In connection with the specific features of the application of traditional complex algorithm (TCA) to the optimization design in engineering structures, an improved method, colony complex algorithm (CCA), was developed based on the optimal combination of many complexes, in which the disadvantages of TCA were overcame. The optimized results of benchmark function show that CCA has better optimizing performance than TCA. CCA was applied to the high-pressure heater optimization design, and the optimization effect is obvious. (authors)

Progress in fission product nuclear data. No. 13

International Nuclear Information System (INIS)

Lammer, M.

1990-11-01

This is the 13th issue of a report series published by the Nuclear Data Section of the IAEA. The types of activities included are measurements, compilations and evaluations of: Fission product yields (neutron induced and spontaneous fission), neutron reaction cross-sections of fission products, data related to the radioactive decay of fission products, delayed neutron data of fission products and bumped fission product data (decay heat, absorption, etc.). The first part of the report consists of unaltered original data which the authors have sent to IAEA/NDS. The second part contains some recent references relative to fission product nuclear data, which were not covered by the contributions submitted, and selected papers from conferences. Part 3 contains requirements for further measurements

The behavior of fission products during nuclear rocket reactor tests

International Nuclear Information System (INIS)

Bokor, P.C.; Kirk, W.L.; Bohl, R.J.

1991-01-01

Fission product release from nuclear rocket propulsion reactor fuel is an important consideration for nuclear rocket development and application. Fission product data from the last six reactors of the Rover program are collected in this paper to provide as basis for addressing development and testing issues. Fission product loss from the fuel will depend on fuel composition and reactor design and operating parameters. During ground testing, fission products can be contained downstream of the reactor. The last Rover reactor tested, the Nuclear Furnance, was mated to an effluent clean-up system that was effective in preventing the discharge of fission products into the atmosphere

Production of technetium-99m in the Institute of Nuclear Physics of the National Nuclear Center of the Republic of Kazakhstan

International Nuclear Information System (INIS)

Chakrov, P.V.; Bannykh, V.I.; Chakrova, E.T.; Tamaeva, K.; Zhotabaev, Zh.R.

2002-01-01

Institute of Nuclear Physics NNC RK, Almaty, Kazakhstan 'National Nuclear Center, Kurchatov, Kazakhstan In order to organize local production of Technetium-99m radiopharmaceutical in Kazakhstan, research, development and technological work has been carried out at the Laboratory of Radiochemistry, Institute of Nuclear Physics NNC RK, in the period of 1999-2001. The technology developed is based on the so-called 'gel method', which allows to use activated natural molybdenum for production of pertechnetate solution with high radioactive concentration. Along with development of chemical process and design of central Tc-generator, a significant attention was paid to installation of quality control techniques. Complex quality control of technetium eluate from the central gel-type generator was performed, including determination of radionuclidic purity, radiochemical purity, chemical composition, content of elemental impurities, sterility, etc. It was found that pertechnetate produced meets the requirements of Russian and European Pharmacopoeias. High quality of radiopharmaceutical was confirmed subsequently in both pre-clinical and clinical tests performed by three medical centers in Almaty. 72 diagnostic examinations of patients with various diagnoses have been carried out during clinical tests. The radiopharmaceutical S odium pertechnetate solution, Tc-99m produced in the Institute of Nuclear Physics NNC RK is officially registered and permitted for use in Kazakhstan, and its regular supply to Almaty clinics has been started in the year 2002

Environmental assessment report: Nuclear Test Technology Complex

International Nuclear Information System (INIS)

Tonnessen, K.; Tewes, H.A.

1982-08-01

The US Department of Energy (USDOE) is planning to construct and operate a structure, designated the Nuclear Test Technology Complex (NTTC), on a site located west of and adjacent to the Lawrence Livermore National Laboratory. The NTTC is designed to house 350 nuclear test program personnel, and will accommodate the needs of the entire staff of the continuing Nuclear Test Program (NTP). The project has three phases: land acquisition, facility construction and facility operation. The purpose of this environmental assessment report is to describe the activities associated with the three phases of the NTTC project and to evaluate potential environmental disruptions. The project site is located in a rural area of southeastern Alameda County, California, where the primary land use is agriculture; however, the County has zoned the area for industrial development. The environmental impacts of the project include surface disturbance, high noise levels, possible increases in site erosion, and decreased air quality. These impacts will occur primarily during the construction phase of the NTTC project and can be mitigated in part by measures proposed in this report

Simulation methods for nuclear production scheduling

International Nuclear Information System (INIS)

Miles, W.T.; Markel, L.C.

1975-01-01

Recent developments and applications of simulation methods for use in nuclear production scheduling and fuel management are reviewed. The unique characteristics of the nuclear fuel cycle as they relate to the overall optimization of a mixed nuclear-fossil system in both the short-and mid-range time frame are described. Emphasis is placed on the various formulations and approaches to the mid-range planning problem, whose objective is the determination of an optimal (least cost) system operation strategy over a multi-year planning horizon. The decomposition of the mid-range problem into power system simulation, reactor core simulation and nuclear fuel management optimization, and system integration models is discussed. Present utility practices, requirements, and research trends are described. 37 references

Future electricity production methods. Part 1: Nuclear energy

International Nuclear Information System (INIS)

Nifenecker, Herve

2011-01-01

The global warming challenge aims at stabilizing the concentrations of Green House Gas (GHG) in the atmosphere. Carbon dioxide is the most effective of the anthropogenic GHG and is essentially produced by consumption of fossil fuels. Electricity production is the dominant cause of CO 2 emissions. It is, therefore, crucial that the share of 'carbon less' electricity production techniques increases at a fast pace. This is the more so, that 'clean' electricity would be useful to displace 'dirty' techniques in other fields such as heat production and transportation. Here we examine the extent to which nuclear energy could be operational in providing 'clean' electricity. A nuclear intensive scenario is shown to give the possibility to divide CO 2 emissions by a factor of 2 worldwide, within 50 years. However, the corresponding sharp increase in nuclear power will put a heavy burden on uranium reserves and will necessitate the development of breeding reactors as soon as possible. A review of present and future reactors is given with special attention to the safety issues. The delicate question of nuclear fuel cycle is discussed concerning uranium reserves and management of used fuels. It is shown that dealing with nuclear wastes is more a socio-political problem than a technical one. The third difficult question associated with the development of nuclear energy is the proliferation risk. It is advocated that, while this is, indeed, a very important question, it is only weakly related to nuclear power development. Finally, the possibilities of nuclear fusion are discussed and it is asserted that, under no circumstances, could nuclear fusion give a significant contribution to the solution of the energy problem before 50 years, too late for dealing with the global warming challenge.

Progress in fission product nuclear data

International Nuclear Information System (INIS)

Lammer, G.

1976-05-01

The purpose of this series is to inform scientists working on Fission Product Nuclear Data, or using such data, about all activities in this field which are planned, ongoing, or have recently been completed. This report consists of reproductions of essentially unaltered original contributions which the authors have sent to IAEA/NDS. The types of activities being included in this report are measurements, compilations and evaluations of: fission product yields; neutron cross-section data of fission products; data related to β-, γ-decay of fission products; delayed neutron data; and fission product decay-heat

Nuclear inelastic scattering of synchrotron radiation on solutions of 57Fe complexes

International Nuclear Information System (INIS)

Vanko, Gy.; Vertes, A.; Bottyan, L.; Nagy, D.L.; Szilagyi, E.

2000-01-01

Nuclear inelastic resonant scattering of synchrotron radiation was applied to the study solutions of 57 Fe complexes. In order to reveal different inelastic contributions solutions of two different 57 Fe complexes of different molecular dimensions with solvents of substantially different viscosities were studied. We argue that the only former experiment available in the literature overestimates the role of the diffusivity in affecting the spectrum. The first direct observation of an intramolecular vibrational transition assisting the nuclear resonance absorption in a liquid is reported. (author)

Technical Integration of Nuclear Hydrogen Production Technology

International Nuclear Information System (INIS)

Lee, Ki Young; Chang, J. H.; Park, J. K.

2007-06-01

These works focus on the development of attainment indices for nuclear hydrogen key technologies, the analysis of the hydrogen production process and the performance estimation for hydrogen production system, and the assessment of the nuclear hydrogen production economy. To estimate the attainments of the key technologies in progress with the performance goals of GIF, itemized are the attainment indices based on SRP published in VHTR R and D steering committee of Gen-IV. For assessing the degree of attainments in comparison with the final goals of VHTR technologies in progress of researches, subdivided are the prerequisite items conformed to the NHDD concepts established in a preconceptual design in 2005. The codes for analyzing the hydrogen production economy are developed for calculating the unit production cost of nuclear hydrogen. We developed basic R and D quality management methodology to meet design technology of VHTR's needs. By putting it in practice, we derived some problems and solutions. We distributed R and D QAP and Q and D QAM to each teams and these are in operation. Computer simulations are performed for estimating the thermal efficiency for the electrodialysis component likely to adapting as one of the hydrogen production system in Korea and EED-SI process known as the key components of the hydrogen production systems. Using the commercial codes, the process diagrams and the spread-sheets were produced for the Bunsen reaction process, Sulphuric Acid dissolution process and HI dissolution process, respectively, which are the key components composing of the SI process

Investigations of nuclear structure and nuclear reactions induced by complex projectiles

International Nuclear Information System (INIS)

Sarantites, D.G.

1993-01-01

This is a progress report on activities of the Washington University group in nuclear reaction studies for the period Sept 1, 1992 to Aug 31, 1993. This group has a research program which touches five areas of nuclear physics: nuclear structure studies at high spin; studies at the interface between structure and reactions; production and study of hot nuclei; reaction mechanism studies; development and use of novel techniques and instrumentation in the above areas of research. Specific activities of the group include in part: superdeformation in 82 Sr; structure of and identical bands in 182 Hg and 178 Pt; a highly deformed band in 136 Pm; particle decay of the 164 Yb compound nucleus; fusion reactions; proton evaporation; two-proton decay of 12 O; modeling and theoretical studies; excited 16 O disassembly into four alpha particles; 209 Bi + 136 Xe collisions at 28.2 MeV/amu; and development work on 4π solid angle gamma detectors, and x-ray detectors

Contributions to the research programs in nuclear and industrial electronics, domestic production of instrumentation, safety and control systems and equipment for nuclear reactors and auxiliary installations

International Nuclear Information System (INIS)

Talpariu, C; Talpariu, J.; Matei, C.

2001-01-01

Domestic production of component system and equipment for the control and safety of nuclear facilities was one of the priority objective of the Nuclear Research Institute Pitesti. The problems addressed were particularly related to design and production of analog and digital equipment for measurements, triggering and display of the values of process parameters as well as to regulating complex functions of this equipment. Associated to this effort were the research works concerning: - reliability and in-service life-time of the electronic components and equipment in the safety and control systems for nuclear processes; - radiation endurance of industrial electronic components; utilization of whirling currents in calandria tube testing; - expert systems and applications in nuclear reactor control and safety; design and testing methods of process real time software packages for safety in control critical systems for nuclear domain. There are presented characteristics of the following equipment: 1. amplifier for ionization chambers with triggering comparator circuits for the CANDU 600 reactor shut down system; 2. amplifier for ionization chambers without triggering comparator circuits for power regulating system; 3. safety and regulating computerized system for C9 and C5 cans; 4. acquisition system for dosimetric data in nuclear facilities; 5. program able digital comparator for the reactor shut down system; 6. stationary gamma areal monitors for CANDU 600 reactors and other nuclear facilities

The Human Nuclear Exosome Targeting Complex Is Loaded onto Newly Synthesized RNA to Direct Early Ribonucleolysis

Directory of Open Access Journals (Sweden)

Michal Lubas

2015-01-01

Full Text Available The RNA exosome complex constitutes the major nuclear eukaryotic 3′-5′ exonuclease. Outside of nucleoli, the human nucleoplasmic exosome is directed to some of its substrates by the nuclear exosome targeting (NEXT complex. How NEXT targets RNA has remained elusive. Using an in vivo crosslinking approach, we report global RNA binding sites of RBM7, a key component of NEXT. RBM7 associates broadly with RNA polymerase II-derived RNA, including pre-mRNA and short-lived exosome substrates such as promoter upstream transcripts (PROMPTs, enhancer RNAs (eRNAs, and 3′-extended products from snRNA and replication-dependent histone genes. Within pre-mRNA, RBM7 accumulates at the 3′ ends of introns, and pulse-labeling experiments demonstrate that RBM7/NEXT defines an early exosome-targeting pathway for 3′-extended snoRNAs derived from such introns. We propose that RBM7 is generally loaded onto newly synthesized RNA to accommodate exosome action in case of available unprotected RNA 3′ ends.

Development of interface technology for nuclear hydrogen production system

International Nuclear Information System (INIS)

Lee, Ki Young; Park, J. K.; Chang, J. H.

2012-06-01

These works focus on the development of attainment indices for nuclear hydrogen key technologies, the analysis of the hydrogen production process and the performance estimation for hydrogen production systems, and the assessment of the nuclear hydrogen production economy. The codes for analyzing the hydrogen production economy are developed for calculating the unit production cost of nuclear hydrogen. We developed basic R and D quality management methodology to meet design technology of VHTR's needs. By putting it in practice, we derived some problems and solutions. We distributed R and D QAP and Q and D QAM to each teams and these are in operation. Computer simulations are performed for estimating the thermal efficiency for the electrodialysis component likely to adapting as one of the hydrogen production system in Korea and EED-SI process known as the key components of the hydrogen production systems. Using the commercial codes, the process diagrams and the spread-sheets were produced for the Bunsen reaction process, Sulphuric Acid dissolution process and HI dissolution process, respectively, which are the key components composing of the SI process

Analytical measurements of fission products during a severe nuclear accident

Science.gov (United States)

Doizi, D.; Reymond la Ruinaz, S.; Haykal, I.; Manceron, L.; Perrin, A.; Boudon, V.; Vander Auwera, J.; tchana, F. Kwabia; Faye, M.

2018-01-01

The Fukushima accident emphasized the fact that ways to monitor in real time the evolution of a nuclear reactor during a severe accident remain to be developed. No fission products were monitored during twelve days; only dose rates were measured, which is not sufficient to carry out an online diagnosis of the event. The first measurements were announced with little reliability for low volatile fission products. In order to improve the safety of nuclear plants and minimize the industrial, ecological and health consequences of a severe accident, it is necessary to develop new reliable measurement systems, operating at the earliest and closest to the emission source of fission products. Through the French program ANR « Projet d'Investissement d'Avenir », the aim of the DECA-PF project (diagnosis of core degradation from fission products measurements) is to monitor in real time the release of the major fission products (krypton, xenon, gaseous forms of iodine and ruthenium) outside the nuclear reactor containment. These products are released at different times during a nuclear accident and at different states of the nuclear core degradation. Thus, monitoring these fission products gives information on the situation inside the containment and helps to apply the Severe Accident Management procedures. Analytical techniques have been proposed and evaluated. The results are discussed here.

Analytical measurements of fission products during a severe nuclear accident

Directory of Open Access Journals (Sweden)

Doizi D.

2018-01-01

Full Text Available The Fukushima accident emphasized the fact that ways to monitor in real time the evolution of a nuclear reactor during a severe accident remain to be developed. No fission products were monitored during twelve days; only dose rates were measured, which is not sufficient to carry out an online diagnosis of the event. The first measurements were announced with little reliability for low volatile fission products. In order to improve the safety of nuclear plants and minimize the industrial, ecological and health consequences of a severe accident, it is necessary to develop new reliable measurement systems, operating at the earliest and closest to the emission source of fission products. Through the French program ANR « Projet d’Investissement d’Avenir », the aim of the DECA-PF project (diagnosis of core degradation from fission products measurements is to monitor in real time the release of the major fission products (krypton, xenon, gaseous forms of iodine and ruthenium outside the nuclear reactor containment. These products are released at different times during a nuclear accident and at different states of the nuclear core degradation. Thus, monitoring these fission products gives information on the situation inside the containment and helps to apply the Severe Accident Management procedures. Analytical techniques have been proposed and evaluated. The results are discussed here.

Ethanol production using nuclear petite yeast mutants

Energy Technology Data Exchange (ETDEWEB)

Hutter, A.; Oliver, S.G. [Department of Biomolecular Sciences, UMIST, Manchester (United Kingdom)

1998-12-31

Two respiratory-deficient nuclear petites, FY23{Delta}pet191 and FY23{Delta}cox5a, of the yeast Saccharomyces cerevisiae were generated using polymerase-chain-reaction-mediated gene disruption, and their respective ethanol tolerance and productivity assessed and compared to those of the parental grande, FY23WT, and a mitochondrial petite, FY23{rho}{sup 0}. Batch culture studies demonstrated that the parental strain was the most tolerant to exogenously added ethanol with an inhibition constant. K{sub i}, of 2.3% (w/v) and a specific rate of ethanol production, q{sub p}, of 0.90 g ethanol g dry cells{sup -1} h{sup -1}. FY23{rho}{sup 0} was the most sensitive to ethanol, exhibiting a K{sub i} of 1.71% (w/v) and q{sub p} of 0.87 g ethanol g dry cells{sup -1} h{sup -1}. Analyses of the ethanol tolerance of the nuclear petites demonstrate that functional mitochondria are essential for maintaining tolerance to the toxin with the 100% respiratory-deficient nuclear petite, FY23{Delta}pet191, having a K{sub i} of 2.14% (w/v) and the 85% respiratory-deficient FY23{Delta}cox5a, having a K{sub i} of 1.94% (w/v). The retention of ethanol tolerance in the nuclear petites as compared to that of FY23{rho}{sup 0} is mirrored by the ethanol productivities of these nuclear mutants, being respectively 43% and 30% higher than that of the respiratory-sufficient parent strain. This demonstrates that, because of their respiratory deficiency, the nuclear petites are not subject of the Pasteur effect and so exhibit higher rates of fermentation. (orig.)

Mesonic atom production in high-energy nuclear collisions

International Nuclear Information System (INIS)

Wakai, M.; Bando, H.; Sano, M.

1987-08-01

The production probability of π-mesonic atom in high-energy nuclear collisions is estimated by a coalescence model. The production cross section is calculated for p + Ne and Ne + Ne systems at 2.1 GeV/A and 5.0 GeV/A beam energy. It is shown that nuclear fragments with larger charge numbers have the advantage in the formation of π-mesonic atoms. The cross section is proportional to Z 3 and of the order of magnitude of 1 ∼ 10 μb in all the above cases. The production cross sections of K-mesonic atoms are also estimated. (author)

Integrated approach to economical, reliable, safe nuclear power production

International Nuclear Information System (INIS)

1982-06-01

An Integrated Approach to Economical, Reliable, Safe Nuclear Power Production is the latest evolution of a concept which originated with the Defense-in-Depth philosophy of the nuclear industry. As Defense-in-Depth provided a framework for viewing physical barriers and equipment redundancy, the Integrated Approach gives a framework for viewing nuclear power production in terms of functions and institutions. In the Integrated Approach, four plant Goals are defined (Normal Operation, Core and Plant Protection, Containment Integrity and Emergency Preparedness) with the attendant Functional and Institutional Classifications that support them. The Integrated Approach provides a systematic perspective that combines the economic objective of reliable power production with the safety objective of consistent, controlled plant operation

From weapons to waste: The future of the nuclear weapons complex

International Nuclear Information System (INIS)

Wasserman Goodman, Sherri

1992-01-01

This paper examines how decision-making power has shifted within the nuclear weapons complex, from the federal government operating agency, in which power was originally vested by the Atomic Energy Act, to the states and to regulatory authorities. Additionally, when the original operating agency, the Atomic Energy Commission (AEC), was abolished in the 1970s, substantial decision-making power shifted from Washington to the field sites. This paper identifies the needs for future materials and weapons production, and recommends that restart of old plants be abandoned as no longer militarily necessary. Instead, the U. S. should take advantage of what may be a unique opportunity to 'leapfrog' to new, smaller, technologically-advanced plants that will meet the needs of the nuclear arsenal in the post-Cold War world. This paper then looks at the current state of DOE's environmental restoration/waste management program, and the technological, legal and political problems it faces in trying to accomplish its mission of cleaning up all nuclear weapons sites. This paper argues that the U. S. government no longer has the exclusive authority to make and carry out critical decisions affecting a cleanup program that will cost the U. S. over $200 billion over the next 20-40 years. Moreover, there are competing theories about the principles that should guide the cleanup program. Finally, the author examines alternative futures for the DOE'S environmental restoration/waste management program. (author)

Complex program of advance in science and technology

International Nuclear Information System (INIS)

Sychev, V.V.

1986-01-01

A draft of the complex program of advance in science and technology of the CMEA member-countries is described in brief. The basis of the program includes five priority trends electronics development complex automatization, advanced development of nuclear energy, production of new materials and tecnologies of their production and processing, advanced developmen of biotechnologies. Development of nuclear energy will be based on WWER-440 and WWER-1000 type NPPs. Heat-only nuclear stations and power and heat nuclear stations will receive a large development effort, as well as sodium-cooled fast reactors of the BN type having 800 and 1600 MW capacity, high-temperature gas-cooled breeders of the BGR-300 type, gas-cooled reactors of the VG-400 type for high-temperature heat supply (500-1000 deg C). It is contemplated to design the TOKAMAK-15 research thermonuclear facility and a pilot thermonuclear reactor for power generation and plutonium production. The program also comprises works aimed at improving reliability and safety of the nuclear installations

Structural insights into SUN-KASH complexes across the nuclear envelope

Institute of Scientific and Technical Information of China (English)

Wenjia Wang; Zhaocai Zhou; Zhubing Shi; Shi Jiao; Cuicui Chen; Huizhen Wang; Guoguang Liu; Qiang Wang; Yun Zhao; Mark I Greene

2012-01-01

Linker of the nucleoskeleton and the cytoskeleton (LINC) complexes are composed of SUN and KASH domaincontaining proteins and bridge the inner and outer membranes of the nuclear envelope.LINC complexes play critical roles in nuclear positioning,cell polarization and cellular stiffness.Previously,we reported the homotrimeric structure of human SUN2.We have now determined the crystal structure of the human SUN2-KASH complex.In the complex structure,the SUN domain homotrimer binds to three independent "hook"-like KASH peptides.The overall conformation of the SUN domain in the complex closely resembles the SUN domain in its apo state.A major conformational change involves the AA'-loop of KASH-bound SUN domain,which rearranges to form a mini β-sheet that interacts with the KASH peptide.The PPPT motif of the KASH domain fits tightly into a hydrophobic pocket on the homotrimeric interface of the SUN domain,which we termed the BI-pocket.Moreover,two adjacent protomers of the SUN domain homotrimer sandwich the KASH domain by hydrophobic interaction and hydrogen bonding.Mutations of these binding sites disrupt or reduce the association between the SUN and KASH domains in vitro.In addition,transfection of wild-type,but not mutant,SUN2 promotes cell migration in Ovcar-3 cells.These results provide a structural model of the LINC complex,which is essential for additional study of the physical and functional coupling between the cytoplasm and the nucleoplasm.

Model of a Nuclear Security Naval Agency for radiation control of the Industrial Complex of of Submarine Construction and Maintenance Ship with Nuclear Propulsion

International Nuclear Information System (INIS)

Lins Junior, Amilton de Sousa

2017-01-01

Due to the construction, by Brazilian Navy, of a Submarine Construction and Maintenance Ship with Nuclear Propulsion, where, among other activities, the commissioning and exchange of the fuel elements of the reactor in the future Nuclear Submarine, and of a Naval Base where the Nuclear Submarine and the Conventional Submarines, it is necessary the establishment of a Nuclear Security Naval Agency to monitor activities involving ionizing radiation sources and nuclear materials aimed at the radiological protection of exposed occupationally individuals (IOE), the general public and the environment. It should be noted that nuclear and radioactive material will be present only in a part of the yard called Radiological Complex. Therefore, the development of a structure for the control of the Radiological Complex is fundamental, considering that the future licensing process will be unprecedented in Brazil and will face several difficulties. This work presents a model of a structure for the radiological control of the industrial complex for the construction and maintenance of the submarine with nuclear propulsion, as well as the fundamental concepts of the activities, such as inspection, regulations and authorizations, to be carried out by the various component sectors of the Nuclear Security Naval Agency. (author)

Identifying cognitive complexity factors affecting the complexity of procedural steps in emergency operating procedures of a nuclear power plant

International Nuclear Information System (INIS)

Park, Jinkyun; Jeong, Kwangsup; Jung, Wondea

2005-01-01

In complex systems such as a nuclear and chemical plant, it is well known that the provision of understandable procedures that allow operators to clarify what needs to be done and how to do it is one of the requisites to secure their safety. As a previous study in providing understandable procedures, the step complexity (SC) measure that can quantify the complexity of procedural steps in emergency operating procedures (EOPs) of a nuclear power plant (NPP) was suggested. However, the necessity of additional complexity factors that can consider a cognitive aspect in evaluating the complexity of procedural steps is raised. To this end, the comparisons between operators' performance data measured by the form of a step performance time with their behavior in carrying out the prescribed activities of procedural steps are conducted in this study. As a result, two kinds of complexity factors (the abstraction level of knowledge and the level of engineering decision) that could affect an operator's cognitive burden are identified. Although a well-designed experiment is indispensable for confirming the appropriateness of the additional complexity factors, it is strongly believed that the change of operators' performance data can be more authentically explained if the additional complexity factors are taken into consideration

Identifying cognitive complexity factors affecting the complexity of procedural steps in emergency operating procedures of a nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Park, Jinkyun [Integrated Safety Assessment Division, Korea Atomic Energy Research Institute, P.O. Box 105, Duckjin-Dong, Yusong-Ku, Taejon 305-600 (Korea, Republic of)]. E-mail: kshpjk@kaeri.re.kr; Jeong, Kwangsup [Integrated Safety Assessment Division, Korea Atomic Energy Research Institute, P.O. Box 105, Duckjin-Dong, Yusong-Ku, Taejon 305-600 (Korea, Republic of); Jung, Wondea [Integrated Safety Assessment Division, Korea Atomic Energy Research Institute, P.O. Box 105, Duckjin-Dong, Yusong-Ku, Taejon 305-600 (Korea, Republic of)

2005-08-01

In complex systems such as a nuclear and chemical plant, it is well known that the provision of understandable procedures that allow operators to clarify what needs to be done and how to do it is one of the requisites to secure their safety. As a previous study in providing understandable procedures, the step complexity (SC) measure that can quantify the complexity of procedural steps in emergency operating procedures (EOPs) of a nuclear power plant (NPP) was suggested. However, the necessity of additional complexity factors that can consider a cognitive aspect in evaluating the complexity of procedural steps is raised. To this end, the comparisons between operators' performance data measured by the form of a step performance time with their behavior in carrying out the prescribed activities of procedural steps are conducted in this study. As a result, two kinds of complexity factors (the abstraction level of knowledge and the level of engineering decision) that could affect an operator's cognitive burden are identified. Although a well-designed experiment is indispensable for confirming the appropriateness of the additional complexity factors, it is strongly believed that the change of operators' performance data can be more authentically explained if the additional complexity factors are taken into consideration.

Identifying cognitive complexity factors affecting the complexity of procedural steps in emergency operating procedures of a nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Jinkyun Park; Kwangsup Jeong; Wondea Jung [Korea Atomic Energy Research Institute, Taejon (Korea). Integrated Safety Assessment Division

2005-08-15

In complex systems such as a nuclear and chemical plant, it is well known that the provision of understandable procedures that allow operators to clarify what needs to be done and how to do it is one of the requisites to secure their safety. As a previous study in providing understandable procedures, the step complexity (SC) measure that can quantify the complexity of procedural steps in emergency operating procedures (EOPs) of a nuclear power plant (NPP) was suggested. However, the necessity of additional complexity factors that can consider a cognitive aspect in evaluating the complexity of procedural steps is raised. To this end, the comparisons between operator' performance data measured by the form of a step performance time with their behavior in carrying out the prescribed activities of procedural steps are conducted in this study. As a result, two kinds of complexity factors (the abstraction level of knowledge and the level of engineering decision) that could affect an operator's cognitive burden are identified. Although a well-designed experiment is indispensable for confirming the appropriateness of the additional complexity factors, it is strongly believed that the change of operators' performance data can be more authentically explained if the additional complexity factors are taken into consideration. (author)

Selection and development of advanced nuclear fuel products

International Nuclear Information System (INIS)

Stucker, David L.; Miller, Richard S.; Arnsberger, Peter L.

2004-01-01

The highly competitive international marketplace requires a continuing product development commitment, short development cycle times and timely, on-target product development to assure customer satisfaction and continuing business. Westinghouse has maintained its leadership position within the nuclear fuel industry with continuous developments and improvements to fuel assembly materials and design. This paper presents a discussion of the processes used by Westinghouse in the selection and refinement of advanced concepts for deployment in the highly competitive US and international nuclear fuel fabrication marketplace. (author)

Virtual enterprise model for the electronic components business in the Nuclear Weapons Complex

Energy Technology Data Exchange (ETDEWEB)

Ferguson, T.J.; Long, K.S.; Sayre, J.A. [Sandia National Labs., Albuquerque, NM (United States); Hull, A.L. [Sandia National Labs., Livermore, CA (United States); Carey, D.A.; Sim, J.R.; Smith, M.G. [Allied-Signal Aerospace Co., Kansas City, MO (United States). Kansas City Div.

1994-08-01

The electronic components business within the Nuclear Weapons Complex spans organizational and Department of Energy contractor boundaries. An assessment of the current processes indicates a need for fundamentally changing the way electronic components are developed, procured, and manufactured. A model is provided based on a virtual enterprise that recognizes distinctive competencies within the Nuclear Weapons Complex and at the vendors. The model incorporates changes that reduce component delivery cycle time and improve cost effectiveness while delivering components of the appropriate quality.

Development of indigenous technology at CNEN in the fields of nuclear medicine, nuclear detectors, instrumentation, radioisotope production and application of nuclear techniques

International Nuclear Information System (INIS)

Mafra, O.

1990-01-01

The main objectives of the program developed at CNEN in the field of nuclear medicine, nuclear detectors, instrumentation, radioisotope production and application of nuclear technique are described. (E.G.) [pt

Role of nuclear engineering in the national power complex

International Nuclear Information System (INIS)

Petros'yants, A.M.; Baturov, B.B.

1981-01-01

Role of nuclear power in power engineering and fuel-power system of the country in the whole is discussed. Economic advantages of NPP's as compared with thermal power plants for district heating (TPP) are grounded. Advisability of combined production of thermal and electric power at TPP as compared with separate heat generation at NPP for district heating and electric power generation at NPP is reported. Data on perspectives of development of nuclear engineering in the light of ''Main directions of economic and social development of the USSR in 1981-1985 and up to 1990'' are presented. It is concluded that nuclear power introduction into national economy would bring important technical, economic and social consequences. Large-scale NPP construction would result in radical revision of the industry structure in the whole fuel-power system including output and transport on the base of modern technology and recent scientific-technical achievements providing essential economic and national economic effect essentially higher labour productivity in fuel power branches of industry. Besides, nuclear engineering creates conditions for better preservation of environment, reduction of expenditures for power and fuel transport, bringing industry centres nearer to centres of energy consumption as well as pre-conditions for removing threat of the so-called ''power hunger'' [ru

Characterization of Nuclear Materials Using Complex of Non-Destructive and Mass-Spectroscopy Methods of Measurements

International Nuclear Information System (INIS)

Gorbunova, A.; Kramchaninov, A.

2015-01-01

Information and Analytical Centre for nuclear materials investigations was established in Russian Federation in the February 2 of 2009 by ROSATOM State Atomic Energy Corporation (the order #80). Its purpose is in preventing unauthorized access to nuclear materials and excluding their illicit traffic. Information and Analytical Centre includes analytical laboratory to provide composition and properties of nuclear materials of unknown origin for their identification. According to Regulation the Centre deals with: · identification of nuclear materials of unknown origin to provide information about their composition and properties; · arbitration analyzes of nuclear materials; · comprehensive research of nuclear and radioactive materials for developing techniques characterization of materials; · interlaboratory measurements; · measurements for control and accounting; · confirmatory measurements. Complex of non-destructive and mass-spectroscopy techniques was developed for the measurements. The complex consists of: · gamma-ray techniques on the base of MGAU, MGA and FRAM codes for uranium and plutonium isotopic composition; · gravimetrical technique with gamma-spectroscopy in addition for uranium content; · calorimetric technique for plutonium mass; · neutron multiplicity technique for plutonium mass; · measurement technique on the base of mass-spectroscopy for uranium isotopic composition; · measurement technique on the base of mass-spectroscopy for metallic impurities. Complex satisfies the state regulation requirements of ensuring the uniformity of measurements including the Russian Federation Federal Law on Ensuring the Uniformity of Measurements #102-FZ, Interstate Standard GOST R ISO/IEC 17025-2006, National Standards of Russian Federation GOST R 8.563-2009, GOST R 8.703-2010, Federal Regulations NRB-99/2009, OSPORB 99/2010. Created complex is provided in reference materials, equipment end certificated techniques. The complex is included in accredited

Exposures resulting from nuclear power production. Annex F

International Nuclear Information System (INIS)

1982-01-01

This Annex assesses the releases of radioactive materials from the nuclear fuel cycle and their resulting dose commitments to the public. The nuclear fuel cycle includes the mining and milling of uranium ores, conversion to nuclear fuel materials, fabrication of fuel elements, production of power in the nuclear reactor, reprocessing of irradiated fuel and recycling of fissile and fertile nuclides recovered, and disposal of radioactive wastes. This Annex also reviews reactor accidents which have led to unplanned releases of activity into the environment, together with estimates of the resulting collective doses.

Organic analyses of mixed nuclear wastes

International Nuclear Information System (INIS)

Toste, A.P.; Lucke, R.B.; Lechner-Fish, T.J.; Hendren, D.J.; Myers, R.B.

1987-04-01

Analytical methods are being developed for the organic analysis of nuclear wastes. Our laboratory analyzed the organic content of three commercial wastes and an organic-rich, complex concentrate waste. The commercial wastes contained a variety of hydrophobic and hydrophilic organics, at concentrations ranging from nanomolar to micromolar. Alkyl phenols, chelating and complexing agents, as well as their degradation products, and carboxylic acids were detected in the commercial wastes. The complex concentrate waste contained chelating and complexing agents, as well as numerous degradation products, at millimolar concentrations. 75.1% of the complex concentrate waste's total organic carbon content has been identified. The presence of chelator fragments in all of the wastes analyzed, occasionally at elevated concentrations, indicates that organic diagenesis, or degradation, in nuclear wastes is both widespread and quite vigorous. 23 refs., 3 tabs

Managing complexity of product mix and production flow in configure-to-order production systems

DEFF Research Database (Denmark)

Myrodia, Anna; Bonev, Martin; Hvam, Lars

2014-01-01

In designing configure-to-order production systems for a growing product variety, companies are challenged with an increased complexity for obtaining high productivity levels and cost-effectiveness. In academia several optimization methods and conceptual frameworks for substituting components, or...

Molten salts and nuclear energy production

International Nuclear Information System (INIS)

Le Brun, Christian

2007-01-01

Molten salts (fluorides or chlorides) were considered near the beginning of research into nuclear energy production. This was initially due to their advantageous physical and chemical properties: good heat transfer capacity, radiation insensitivity, high boiling point, wide range solubility for actinides. In addition it was realised that molten salts could be used in numerous situations: high temperature heat transfer, core coolants with solid fuels, liquid fuel in a molten salt reactor, solvents for spent nuclear solid fuel in the case of pyro-reprocessing and coolant and tritium production in the case of fusion. Molten salt reactors, one of the six innovative concepts chosen by the Generation IV international forum, are particularly interesting for use as either waste incinerators or thorium cycle systems. As the neutron balance in the thorium cycle is very tight, the possibility to perform online extraction of some fission product poisons from the salt is very attractive. In this article the most important questions that must be addressed to demonstrate the feasibility of molten salt reactor will be reviewed

Nuclear H2 production - a utility perspective

International Nuclear Information System (INIS)

Keuter, D.

2010-01-01

Entergy is the second largest nuclear owner/operator in the United States with five nuclear units in the south operating under a cost of service structure and an additional six units in the Northeast and Midwest operating as merchant generating facilities. As a major nuclear operator in the merchant sector, Entergy wears the risk of nuclear operations - revenues are directly dependent upon operational performance. Our investment in merchant nuclear operations reflects our belief that use of nuclear energy in the competitive merchant environment can be an economically viable business venture. Over the past 10 years, our success in the merchant sector has led to our support for the expanded use of nuclear energy and more specifically the development and deployment of advanced nuclear technologies. Of particular interest today is Entergy's support for the development of HTGR - nuclear technologies that can expand the application of nuclear energy into the broader energy marketplace. Studies and economic evaluations, thus far, have indicated that HTGR can compete with premium fossil fuels in supplying process heat for industrial processes and may well become competitive in the production of hydrogen for the bulk market. We believe that the application of nuclear energy in the broader energy marketplace is of vital importance to our nation's energy security and as an experienced merchant nuclear operator, we believe that business opportunities in this broader energy market will emerge. (author)

Economical analysis of biofuel products and nuclear plant hydrogen

International Nuclear Information System (INIS)

Edwaren Liun

2011-01-01

The increasing in oil prices over the last six years is unprecedented that should be seen as a spur to increased efficiency. The surge in oil prices on the world market today is driven by strong demand factors in the depletion of world oil reserves. To replace the fuel oil from the bowels of the earth the various alternatives should be considered, including other crops or vegetable oil production of bio-fuels and hydrogen are produced by high temperature nuclear reactors. Biofuels in the form of ethanol made from corn or sugar cane and biodiesel made from palm oil or jatropha. With the latest world oil prices, future fuel vegetable oil and nuclear hydrogen-based energy technologies become popular in various parts of the world. Economics of biodiesel will be changed in accordance with world oil prices and subsidy regulations which apply to fuel products. On the other hand the role of nuclear energy in hydrogen production with the most potential in the techno-economics is a form of high temperature steam electrolysis, using heat and electricity from nuclear reactors. The production cost of biodiesel fuel on the basis of ADO type subsidy is 10.49 US$/MMBTU, while the production cost of hydrogen as an energy carrier of high temperature reactor is 15.30 US$/MMBTU. Thus, both types seem to have strong competitiveness. (author)

Nuclear power desalinating complex with IRIS reactor plant and Russian distillation desalinating unit

International Nuclear Information System (INIS)

Kostin, V. I.; Panov, Yu.K.; Polunichev, V. I.; Fateev, S. A.; Gureeva, L. V.

2004-01-01

This paper has been prepared as a result of Russian activities on the development of nuclear power desalinating complex (NPDC) with the IRIS reactor plant (RP). The purpose of the activities was to develop the conceptual design of power desalinating complex (PDC) and to evaluate technical and economical indices, commercial attractiveness and economical efficiency of PDC based on an IRIS RP with distillation desalinating plants. The paper presents the main results of studies as applied to dual-purpose PDC based on IRIS RP with different types of desalinating plants, namely: characteristics of nuclear power desalinating complex based on IRIS reactor plant using Russian distillation desalinating technologies; prospective options of interface circuits of the IRIS RP with desalinating plants; evaluations of NPDC with IRIS RP output based on selected desalinating technologies for water and electric power supplied to the grid; cost of water generated by NPDC for selected interface circuits made by the IAEA DEEP code as well as by the Russian TEO-INVEST code; cost evaluation results for desalinated water of PDC operating on fossil fuel and conditions for competitiveness of the nuclear PDC based on IRIS RP compared with analog desalinating complexes operating on fossil fuel.(author)

Complex-energy approach to sum rules within nuclear density functional theory

Science.gov (United States)

Hinohara, Nobuo; Kortelainen, Markus; Nazarewicz, Witold; Olsen, Erik

2015-04-01

Background: The linear response of the nucleus to an external field contains unique information about the effective interaction, the correlations governing the behavior of the many-body system, and the properties of its excited states. To characterize the response, it is useful to use its energy-weighted moments, or sum rules. By comparing computed sum rules with experimental values, the information content of the response can be utilized in the optimization process of the nuclear Hamiltonian or the nuclear energy density functional (EDF). But the additional information comes at a price: compared to the ground state, computation of excited states is more demanding. Purpose: To establish an efficient framework to compute energy-weighted sum rules of the response that is adaptable to the optimization of the nuclear EDF and large-scale surveys of collective strength, we have developed a new technique within the complex-energy finite-amplitude method (FAM) based on the quasiparticle random-phase approximation (QRPA). Methods: To compute sum rules, we carry out contour integration of the response function in the complex-energy plane. We benchmark our results against the conventional matrix formulation of the QRPA theory, the Thouless theorem for the energy-weighted sum rule, and the dielectric theorem for the inverse-energy-weighted sum rule. Results: We derive the sum-rule expressions from the contour integration of the complex-energy FAM. We demonstrate that calculated sum-rule values agree with those obtained from the matrix formulation of the QRPA. We also discuss the applicability of both the Thouless theorem about the energy-weighted sum rule and the dielectric theorem for the inverse-energy-weighted sum rule to nuclear density functional theory in cases when the EDF is not based on a Hamiltonian. Conclusions: The proposed sum-rule technique based on the complex-energy FAM is a tool of choice when optimizing effective interactions or energy functionals. The method

Nuclear Forensics and Radiochemistry: Reaction Networks

Energy Technology Data Exchange (ETDEWEB)

Rundberg, Robert S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-11-22

In the intense neutron flux of a nuclear explosion the production of isotopes may occur through successive neutron induced reactions. The pathway to these isotopes illustrates both the complexity of the problem and the need for high quality nuclear data. The growth and decay of radioactive isotopes can follow a similarly complex network. The Bateman equation will be described and modified to apply to the transmutation of isotopes in a high flux reactor. A alternative model of growth and decay, the GD code, that can be applied to fission products will also be described.

Natural disease course and genotype-phenotype correlations in Complex I deficiency caused by nuclear gene defects

DEFF Research Database (Denmark)

Koene, S; Rodenburg, R J; van der Knaap, M S

2012-01-01

cases and 126 from literature) with mutations in nuclear genes encoding structural complex I proteins or those involved in its assembly. Complex I deficiency caused by a nuclear gene defect is usually a non-dysmorphic syndrome, characterized by severe multi-system organ involvement and a poor prognosis...

Investigations of nuclear structure and nuclear reactions induced by complex projectiles

International Nuclear Information System (INIS)

Sarantites, D.G.

1992-01-01

The research program described touches five areas of nuclear physics: nuclear structure studies at high spin (hyperdeformation in the mass A ≅ 182 region, structure of 182 Hg and 182 Au at high spin, a highly deformed band in 136 Pm and the anomalous h 11/2 proton crossing in the A∼135 superdeformed region), studies at the interface between structure and reactions (population of entry states in heavy-ion fusion reactions, nuclear structure effects in proton evaporation spectra, nuclear structure- dependent entry state population by total spectroscopy, entrance channel effects in fusion near the barrier, lifetimes of subbarrier α particles by the atomic clock method), production and study of hot nuclei (the statistical model evaporation code EVAP, statistical emission of deuterons and tritons from highly excited compound nuclei, heavy-fragment emission as a probe of the thermal properties of highly excited compound nuclei, use of incoming-wave boundary condition transmission coefficients in the statistical model: implications in the particle evaporation spectra, study of transparency in the optical model), reaction mechanism studies (binary character of highly dissipative 209 Bi + 136 Xe collisions at E/A=28.2 MeV), and development and use of novel techniques and instrumentation in these areas of research (including a 4π channel selection device, a novel x-ray detector, and a simple channel-selecting detector)

Nuclear fuel production

International Nuclear Information System (INIS)

Randol, A.G.

1985-01-01

The production of new fuel for a power plant reactor and its disposition following discharge from the power plant is usually referred to as the ''nuclear fuel cycle.'' The processing of fuel is cyclic in nature since sometime during a power plant's operation old or ''depleted'' fuel must be removed and new fuel inserted. For light water reactors this step typically occurs once every 12-18 months. Since the time required for mining of the raw ore to recovery of reusable fuel materials from discharged materials can span up to 8 years, the management of fuel to assure continuous power plant operation requires simultaneous handling of various aspects of several fuel cycles, for example, material is being mined for fuel to be inserted in a power plant 2 years into the future at the same time fuel is being reprocessed from a discharge 5 years prior. Important aspects of each step in the fuel production process are discussed

JNDC nuclear data library of fission products

International Nuclear Information System (INIS)

Tasaka, Kanji; Ihara, Hitoshi; Akiyama, Masatsugu; Yoshida, Tadashi; Matumoto, Zyun-itiro; Nakasima, Ryuzo

1983-10-01

The JNDC (Japanese Nuclear Data Committee) FP (Fission Product) nuclear data library for 1172 fission products is described in this report. The gross theory of beta decay has been used extensively for estimating unknown decay data and also some of known decay data with poor accuracy. The calculated decay powers of fission products using the present library show excellent agreement with the latest measurements at ORNL (Oak Ridge National Laboratory), LANL (Los Alamos National Laboratory) and UTT (University of Tokyo, Tokai) for cooling times shorter than 10 3 s after irradiation. The calculated decay powers by the existing libraries showed systematic deviations at short cooling times; the calculated beta and gamma decay powers after burst fission were smaller than the experimental results for cooling times shorter than 10 s, and in the cooling time range 10 to 10 3 s the beta-decay power was larger than the measured values and the gamma decay power smaller than the measured results. The present JNDC FP nuclear data library resolved these discrepancies in the short cooling time ranges. The decay power of fission products has been calculated for ten fission types and the results have been fitted by an analytical function with 31 exponentials. This permits the easy application of the present results of decay power calculations to a LOCA (Loss-of-Coolant Accident) analysis of a light water reactor and so on. (author)

Development of the production of special steels for nuclear industries

International Nuclear Information System (INIS)

Vieillard-Baron, B.

1977-01-01

The development of electro-nuclear industries has a powerful impact on the production of special steels, although the quantity of material applied to the non-conventional parts of nuclear power plants is quite small as compared to the total production requirements in this industrial field. Evolution bears on the product research, development and testing methods, on the technical and marketing services - in particular the establishment of quality control teams and assurance manuals - and the implementation of high performance production equipments. Manufacturing must however take place under normal work load and productivity conditions of production tools, and thus ensure a satisfactory profitability on investments entailed [fr

DNA origami scaffold for studying intrinsically disordered proteins of the nuclear pore complex

NARCIS (Netherlands)

Ketterer, Philip; Ananth, Adithya N; Laman Trip, Diederik S; Mishra, Ankur; Bertosin, Eva; Ganji, Mahipal; van der Torre, Jaco; Onck, Patrick; Dietz, Hendrik; Dekker, Cees

2018-01-01

The nuclear pore complex (NPC) is the gatekeeper for nuclear transport in eukaryotic cells. A key component of the NPC is the central shaft lined with intrinsically disordered proteins (IDPs) known as FG-Nups, which control the selective molecular traffic. Here, we present an approach to realize

Subsumed complexity: abiogenesis as a by-product of complex energy transduction

Science.gov (United States)

Adam, Z. R.; Zubarev, D.; Aono, M.; Cleaves, H. James

2017-11-01

The origins of life bring into stark relief the inadequacy of our current synthesis of thermodynamic, chemical, physical and information theory to predict the conditions under which complex, living states of organic matter can arise. Origins research has traditionally proceeded under an array of implicit or explicit guiding principles in lieu of a universal formalism for abiogenesis. Within the framework of a new guiding principle for prebiotic chemistry called subsumed complexity, organic compounds are viewed as by-products of energy transduction phenomena at different scales (subatomic, atomic, molecular and polymeric) that retain energy in the form of bonds that inhibit energy from reaching the ground state. There is evidence for an emergent level of complexity that is overlooked in most conceptualizations of abiogenesis that arises from populations of compounds formed from atomic energy input. We posit that different forms of energy input can exhibit different degrees of dissipation complexity within an identical chemical medium. By extension, the maximum capacity for organic chemical complexification across molecular and macromolecular scales subsumes, rather than emerges from, the underlying complexity of energy transduction processes that drive their production and modification. This article is part of the themed issue 'Reconceptualizing the origins of life'.

Nuclear hydrogen production: re-examining the fusion option

International Nuclear Information System (INIS)

Baindur, S.

2007-01-01

This paper describes a scheme for nuclear hydrogen production by fusion. The basic idea is to use nuclear energy of the fuel (hydrogen plasma) to produce molecular hydrogen fro carbon-free hydrogen compounds. The hydrogen is then stored and utilized electrochemically in fuel cells or chemically as molecular hydrogen in internal combustion engines

Nuclear models and data for gamma-ray production

International Nuclear Information System (INIS)

Young, P.G.

1975-01-01

The current Evaluated Nuclear Data File (ENDF/B, Version IV) contains information on prompt gamma-ray production from neutron-induced reactions for some 38 nuclides. In addition, there is a mass of fission product yield, capture, and radioactive decay data from which certain time-dependent gamma-ray results can be calculated. These data are needed in such applications as gamma-ray heating calculations for reactors, estimates of radiation levels near nuclear facilities and weapons, shielding design calculations, and materials damage estimates. The prompt results are comprised of production cross sections, multiplicities, angular distributions, and energy spectra for secondary gamma-rays from a variety of reactions up to an incident neutron energy of 20 MeV. These data are based in many instances on experimental measurements, but nuclear model calculations, generally of a statistical nature, are also frequently used to smooth data, to interpolate between measurements, and to calculate data in unmeasured regions. The techniques and data used in determining the ENDF/B evaluations are reviewed, and comparisons of model-code calculations and ENDF data with recent experimental results are given. 11 figures

Progress in fission product nuclear data. Information about activities in the field of measurements and compilations/evaluations of fission product nuclear data (FPND)

International Nuclear Information System (INIS)

Lammer, G.

1978-07-01

This is the fourth issue of a report series on Fission Product Nuclear Data (FPND) which is published by the Nuclear Data Section (NDS) of the International Atomic Energy Agency (IAEA). The purpose of this series is to inform scientists working on FPND, or using such data, about all activities in this field which are planned, ongoing, or have recently been completed. The main part of this report consists of unaltered original contributions which the authors have sent to IAEA/NDS. The types of activities being included in this report are measurements, compilations and evaluations of: Fission product yields (neutron induced and spontaneous fission); neutron reaction cross sections of fission products; data related to the radioactive decay of fission products; delayed neutron data of fission products; and lumped fission product data (decay heat, absorption etc.)

DPRK's 4"t"h Nuclear Test and its Tritium Production

International Nuclear Information System (INIS)

Kim, Min Soo; Lee, Sang Joon; Chang, Sun Young

2016-01-01

On January 6, 2016 at 10:30am, the artificial earthquake in the DPRK was detected by multiple international seismic organizations. After 2 hours, the DPRK announced on state TV that 'The first H-bomb test was successfully conducted in the DPRK at 10:00 am on Wednesday, Juche 105(2016), pursuant to the strategic determination of the ruling communist party.' There has been a doubt about the real nature of the DPRK's 4th nuclear test, since 2 months have been passed after its nuclear test. To analyze the nature of the DPRK's nuclear test, it is necessary to check possible options for production of essential materials. The pathways to produce nuclear fusion material (tritium) and to have a relatively high possibility for the DPRK are described in this article. Tritium is key material for H-bomb. And there are two options for the DPRK which are 1) production and 2) illicit trafficking. And this study is focused on production possibility of DPRK. Determination of the nature of DPRK's nuclear test is very hard issue

The Canadian nuclear power industry. Background paper

International Nuclear Information System (INIS)

Nixon, A.

1993-12-01

Nuclear power, the production of electricity from uranium through nuclear fission, is by far the most prominent segment of the nuclear industry. The value of the electricity produced, $3.7 billion in Canada in 1992, far exceeds the value of any other product of the civilian nuclear industry. Power production employs many more people than any other sector, the capital investment is much greater, and nuclear power plants are much larger and more visible than uranium mining and processing facilities. They are also often located close to large population centres. This paper provides an overview of some of the enormously complex issues surrounding nuclear power. It describes the Canadian nuclear power industry, addressing i particular its performance so far and future prospects. (author). 1 tab

The Canadian nuclear power industry. Background paper

Energy Technology Data Exchange (ETDEWEB)

Nixon, A [Library of Parliament, Ottawa, ON (Canada). Science and Technology Div.

1993-12-01

Nuclear power, the production of electricity from uranium through nuclear fission, is by far the most prominent segment of the nuclear industry. The value of the electricity produced, $3.7 billion in Canada in 1992, far exceeds the value of any other product of the civilian nuclear industry. Power production employs many more people than any other sector, the capital investment is much greater, and nuclear power plants are much larger and more visible than uranium mining and processing facilities. They are also often located close to large population centres. This paper provides an overview of some of the enormously complex issues surrounding nuclear power. It describes the Canadian nuclear power industry, addressing i particular its performance so far and future prospects. (author). 1 tab.

DNA origami scaffold for studying intrinsically disordered proteins of the nuclear pore complex

NARCIS (Netherlands)

Ketterer, Philip; Ananth, A.N.; Laman Trip, J.D.S.; Mishra, Ankur; Bertosin, Eva; Ganji, M.; van der Torre, J.; Onck, Patrick; Dietz, Hendrik; Dekker, C.

2018-01-01

The nuclear pore complex (NPC) is the gatekeeper for nuclear transport in eukaryotic cells. A key component of the NPC is the central shaft lined with intrinsically disordered proteins (IDPs) known as FG-Nups, which control the selective molecular traffic. Here, we present an approach to realize

A systematic method for identifying vital areas at complex nuclear facilities.

Energy Technology Data Exchange (ETDEWEB)

Beck, David Franklin; Hockert, John

2005-05-01

Identifying the areas to be protected is an important part of the development of measures for physical protection against sabotage at complex nuclear facilities. In June 1999, the International Atomic Energy Agency published INFCIRC/225/Rev.4, 'The Physical Protection of Nuclear Material and Nuclear Facilities.' This guidance recommends that 'Safety specialists, in close cooperation with physical protection specialists, should evaluate the consequences of malevolent acts, considered in the context of the State's design basis threat, to identify nuclear material, or the minimum complement of equipment, systems or devices to be protected against sabotage.' This report presents a structured, transparent approach for identifying the areas that contain this minimum complement of equipment, systems, and devices to be protected against sabotage that is applicable to complex nuclear facilities. The method builds upon safety analyses to develop sabotage fault trees that reflect sabotage scenarios that could cause unacceptable radiological consequences. The sabotage actions represented in the fault trees are linked to the areas from which they can be accomplished. The fault tree is then transformed (by negation) into its dual, the protection location tree, which reflects the sabotage actions that must be prevented in order to prevent unacceptable radiological consequences. The minimum path sets of this fault tree dual yield, through the area linkage, sets of areas, each of which contains nuclear material, or a minimum complement of equipment, systems or devices that, if protected, will prevent sabotage. This method also provides guidance for the selection of the minimum path set that permits optimization of the trade-offs among physical protection effectiveness, safety impact, cost and operational impact.

Nuclear desalination and electricity production for islands

International Nuclear Information System (INIS)

Tran Dai Nghiep

2005-01-01

Nuclear desalination is an established and commercially proven technology that is now available and has the potential of further improvement. The technology of a small-sized reactor for desalination and electricity production will be an economically viable option and will also be suitable for islands with geographic, climatic, ecological and hydrological specifics. The operating experiences and achieved safety should benefit the early stage of a national nuclear power programme in developing countries. (author)

Improvement of uranium production efficiency to meet China's nuclear power requirements

International Nuclear Information System (INIS)

Zhang, R.

1997-01-01

Recently China put the Qinshan Nuclear Power Plant, with an installed capacity of 300 MW, in the province of Zhejiang and the Daya Bay Nuclear Power Plant, with a total installed capacity of 2 x 900 MW, in commercial operation. China plans a rapid growth in nuclear power from 1995 to 2010. China's uranium production will therefore also enter a new period with nuclear power increasing. In order to meet the demand of nuclear power for uranium special attention has been paid to both technical progress improvement using management with the aim of reducing the cost of uranium production. The application of the trackless mining technique has enhanced the uranium mining productivity significantly. China has produced a radiometric sorter, model 5421-2 for pre-concentrating uranium run-of-mine ore. This effectively increases the uranium content in mill feed and decreases the operating cost of hydrometallurgical treatment. The in situ leach technique after blasting is applied underground in the Lantian Mine, in addition to the surface heap leaching, and has obtained a perfect result. The concentrated acid-curing, and ferric sulphate trickle leaching process, will soon be used in commercial operation for treating uranium ore grading -5 to -7 mm in size. The annual production capability of the Yining Mine will be extended to 100 tonnes U using improving in situ leaching technology. For the purpose of improving the uranium production efficiency much work has been done optimizing the distribution of production centres. China plans to expand its uranium production to meet the uranium requirements of the developing nuclear power plants. (author). 4 tabs

Complex organizations: the case of the Brazilian nuclear sector

International Nuclear Information System (INIS)

Xavier, Roberto Salles

2009-01-01

The resumption of the Brazilian Nuclear Program (BNP), in the proposed size and after 20 years of paralysis, requires profound changes in the current organizational modeling of the national nuclear industry. The effectiveness of any process of organizational change is limited to three factors. The theoretical bottleneck happens when you do not know enough about a phenomenon in order to effect the desired changes. The resource bottleneck occurs when knowledge may be available to change people's behavior but the funds necessary for implementation may be lacking. The organizational bottleneck emerges when there are knowledge and resources to solve a problem, but may not able to organize the resources in order to carry out the problem-solving effort. In the case of resumption of BNP seems clear that there is the knowledge of what is needed to make policy and the intention to allocate the necessary resources. But the question is the following: the current organizational model of the Brazilian nuclear sector is consistent with the goals laid down in the scenario of resumption of BNP? That is, is there organizational ability to leverage a program of the size proposed for the nuclear area? Find answers to these questions is crucial, because the organizational model of the Brazilian nuclear sector consists of elements involving a complex interorganizational system. Thus, this article is to examine the appropriateness of the current organizational modeling of the Brazilian nuclear sector to current demands of society. As a result, the article aims to propose recommendations for a remodeling of the nuclear sector, taking into account the current national and international scenarios of nuclear energy. (author)

Product Complexity Impact on Quality and Delivery Performance

OpenAIRE

Nielsen, Jeppe Bjerrum; Hvam, Lars

2011-01-01

Existing literature on product portfolio complexity is mainly focused on cost related aspects. It is widely acknowledged that an increase in a company’s product portfolio will lead to an increase in complexity related costs such as order management, procurement and inventory. The objective of this article is to examine which other factors that might be affected when a company is expanding its product portfolio, if initiatives are not taken to accommodate this increase. Empirical work carried ...

Nuclear material production cycle vulnerability analysis

International Nuclear Information System (INIS)

Bott, T.F.

1996-01-01

This paper discusses a method for rapidly and systematically identifying vulnerable equipment in a nuclear material or similar production process and ranking that equipment according to its attractiveness to a malevolent attacker. A multistep approach was used in the analysis. First, the entire production cycle was modeled as a flow diagram. This flow diagram was analyzed using graph theoretical methods to identify processes in the production cycle and their locations. Models of processes that were judged to be particularly vulnerable based on the cycle analysis then were developed in greater detail to identify equipment in that process that is vulnerable to intentional damage

Super-resolution mapping of scaffold nucleoporins in the nuclear pore complex.

Science.gov (United States)

Ma, Jiong; Kelich, Joseph M; Junod, Samuel L; Yang, Weidong

2017-04-01

The nuclear pore complex (NPC), composed of ∼30 different nucleoporins (Nups), is one of the largest supramolecular structures in eukaryotic cells. Its octagonal ring scaffold perforates the nuclear envelope and features a unique molecular machinery that regulates nucleocytoplasmic transport. However, the precise copy number and the spatial location of each Nup in the native NPC remain obscure due to the inherent difficulty of counting and localizing proteins inside of the sub-micrometer supramolecular complex. Here, we combined super-resolution single-point edge-excitation subdiffraction (SPEED) microscopy and nanobody-specific labeling to reveal the spatial distribution of scaffold Nups within three separate layers in the native NPC with a precision of ∼3 nm. Our data reveal both the radial and axial spatial distributions for Pom121, Nup37 and Nup35 and provide evidence for their copy numbers of 8, 32 and 16, respectively, per NPC. This approach can help pave the path for mapping the entirety of Nups in native NPCs and also other structural components of macromolecular complexes. © 2017. Published by The Company of Biologists Ltd.

Methods for forming complex oxidation reaction products including superconducting articles

International Nuclear Information System (INIS)

Rapp, R.A.; Urquhart, A.W.; Nagelberg, A.S.; Newkirk, M.S.

1992-01-01

This patent describes a method for producing a superconducting complex oxidation reaction product of two or more metals in an oxidized state. It comprises positioning at least one parent metal source comprising one of the metals adjacent to a permeable mass comprising at least one metal-containing compound capable of reaction to form the complex oxidation reaction product in step below, the metal component of the at least one metal-containing compound comprising at least a second of the two or more metals, and orienting the parent metal source and the permeable mass relative to each other so that formation of the complex oxidation reaction product will occur in a direction towards and into the permeable mass; and heating the parent metal source in the presence of an oxidant to a temperature region above its melting point to form a body of molten parent metal to permit infiltration and reaction of the molten parent metal into the permeable mass and with the oxidant and the at least one metal-containing compound to form the complex oxidation reaction product, and progressively drawing the molten parent metal source through the complex oxidation reaction product towards the oxidant and towards and into the adjacent permeable mass so that fresh complex oxidation reaction product continues to form within the permeable mass; and recovering the resulting complex oxidation reaction product

Werner complex deficiency in cells disrupts the Nuclear Pore Complex and the distribution of lamin B1.

Science.gov (United States)

Li, Zhi; Zhu, Yizhou; Zhai, Yujia; R Castroagudin, Michelle; Bao, Yifei; White, Tommy E; Glavy, Joseph S

2013-12-01

From the surrounding shell to the inner machinery, nuclear proteins provide the functional plasticity of the nucleus. This study highlights the nuclear association of Pore membrane (POM) protein NDC1 and Werner protein (WRN), a RecQ helicase responsible for the DNA instability progeria disorder, Werner Syndrome. In our previous publication, we connected the DNA damage sensor Werner's Helicase Interacting Protein (WHIP), a binding partner of WRN, to the NPC. Here, we confirm the association of the WRN/WHIP complex and NDC1. In established WRN/WHIP knockout cell lines, we further demonstrate the interdependence of WRN/WHIP and Nucleoporins (Nups). These changes do not completely abrogate the barrier of the Nuclear Envelope (NE) but do affect the distribution of FG Nups and the RAN gradient, which are necessary for nuclear transport. Evidence from WRN/WHIP knockout cell lines demonstrates changes in the processing and nucleolar localization of lamin B1. The appearance of "RAN holes" void of RAN corresponds to regions within the nucleolus filled with condensed pools of lamin B1. From WRN/WHIP knockout cell line extracts, we found three forms of lamin B1 that correspond to mature holoprotein and two potential post-translationally modified forms of the protein. Upon treatment with topoisomerase inhibitors lamin B1 cleavage occurs only in WRN/WHIP knockout cells. Our data suggest the link of the NDC1 and WRN as one facet of the network between the nuclear periphery and genome stability. Loss of WRN complex leads to multiple alterations at the NPC and the nucleolus. © 2013. Published by Elsevier B.V. All rights reserved.

Nuclear data relevant to the production and application of diagnostic radionuclides

International Nuclear Information System (INIS)

Qaim, S.M.

2002-01-01

The types of nuclear data and their quality required in the production and application of diagnostic radionuclides are outlined. The radioactive decay data determine the suitability of a radioisotope for in vivo tracer studies, both from the imaging and internal radiation dose considerations. The nuclear reaction cross section data allow optimisation of production routes. Both reactors and cyclotrons are used for production purposes. The nuclear data needed in the two cases and their present status are discussed. Special attention is paid to radionuclides suitable for emission tomography (PET and SPECT). The controversy about reactor vs cyclotron production of the widely used sup 9 sup 9 Mo/ sup 9 sup 9 sup m Tc generator system is discussed. Some special considerations in cyclotron production of radionuclides are outlined. The need of accurate data near reaction thresholds, the constraint of available particles and their energies at a small cyclotron, the influence of increasing incident particle energy, and the formation of isomeric impurities are discussed in detail. The role of nuclear model calculations in predicting unknown data is considered. (author)

Nuclear hydrogen production programme in the United States

International Nuclear Information System (INIS)

Sink, C.

2010-01-01

The Nuclear Hydrogen Initiative (NHI) is focused on demonstrating the economic, commercial-scale production of hydrogen using process heat derived from nuclear energy. NHI-supported research has concentrated to date on three technologies compatible with the Next Generation Nuclear Plant (NGNP): high temperature steam electrolysis (HTE); sulphur-iodine (S-I) thermochemical; and hybrid sulphur (HyS) thermochemical. In 2009 NHI will down select to a single technology on which to focus its future development efforts, for which the next step will be a pilot-scale experiment. (author)

Technical Integration of Nuclear Hydrogen Production Technology

International Nuclear Information System (INIS)

Lee, Ki Young; Park, J. K.; Chang, J. H.

2009-04-01

These works focus on the development of attainment indices for nuclear hydrogen key technologies, the analysis of the hydrogen production process and the performance estimation for hydrogen production systems, and the assessment of the nuclear hydrogen production cost. For assessing the degree of attainments in comparison with the final goals of VHTR technologies in progress of researches, subdivided are the prerequisite items confirmed to the NHDD concepts. We developed and applied R and D quality management methodology to meet 'Development of Key Technologies for Nuclear Hydrogen' project. And we also distributed R and D QAM and R and D QAP to each teams and are in operation. The preconceptual flow diagrams of SI, HTSE, and HyS processes are introduced and their material and energy balances have been proposed. The hydrogen production thermal efficiencies of not only the SI process as a reference process but also the HTSE and HyS processes were also estimated. Technical feasibility assessments of SI, HTSE, and HyS processes have been carried out by using the pair-wise comparison and analytic hierarchy process, and it is revealed that the experts are considering the SI process as the most feasible process. The secondary helium pathway across the SI process is introduced. Dynamic simulation codes for the H2S04vaporizer, sulfuric acid and sulfur trioxide decomposers, and HI decomposer on the secondary helium pathway and for the primary and secondary sulfuric acid distillation columns, HIx solution distillation column, and preheater for HI vapor have been developed and integrated

Synergistic production of hydrogen using fossil fuels and nuclear energy application of nuclear-heated membrane reformer

International Nuclear Information System (INIS)

Hori, M.; Matsui, K.; Tashimo, M.; Yasuda, I.

2004-01-01

Processes and technologies to produce hydrogen synergistically by the steam reforming reaction using fossil fuels and nuclear heat are reviewed. Formulas of chemical reactions, required heats for reactions, saving of fuel consumption or reduction of carbon dioxide emission, possible processes and other prospects are examined for such fossil fuels as natural gas, petroleum and coal. The 'membrane reformer' steam reforming with recirculation of reaction products in a closed loop configuration is considered to be the most advantageous among various synergistic hydrogen production methods. Typical merits of this method are: nuclear heat supply at medium temperature below 600 deg. C, compact plant size and membrane area for hydrogen production, efficient conversion of feed fuel, appreciable reduction of carbon dioxide emission, high purity hydrogen without any additional process, and ease of separating carbon dioxide for future sequestration requirements. With all these benefits, the synergistic production of hydrogen by membrane reformer using fossil fuels and nuclear energy can be an effective solution in this century for the world which has to use. fossil fuels any way to some extent while reducing carbon dioxide emission. For both the fossil fuels industry and the nuclear industry, which are under constraint of resource, environment and economy, this production method will be a viable symbiosis strategy for the coming hydrogen economy era. (author)

The human cap-binding complex is functionally connected to the nuclear RNA exosome

DEFF Research Database (Denmark)

Andersen, Peter Refsing; Domanski, Michal; Kristiansen, Maiken Søndergaard

2013-01-01

Nuclear processing and quality control of eukaryotic RNA is mediated by the RNA exosome, which is regulated by accessory factors. However, the mechanism of exosome recruitment to its ribonucleoprotein (RNP) targets remains poorly understood. Here we report a physical link between the human exosome...... and the cap-binding complex (CBC). The CBC associates with the ARS2 protein to form CBC-ARS2 (CBCA) and then further connects, together with the ZC3H18 protein, to the nuclear exosome targeting (NEXT) complex, thus forming CBC-NEXT (CBCN). RNA immunoprecipitation using CBCN factors as well as the analysis...

Nuclear energy in metallurgy

Energy Technology Data Exchange (ETDEWEB)

Jirak, Z; Malik, J; Vrba, J

1976-01-01

The present power situation and its estimated development with a view to metallurgy is presented. The possibilities of the development of Czechoslovak metallurgy are described with regard to conventional fuels and to nuclear power applications. The programme of the use of nuclear power in countries with a highly developed metallurgical industry, such as Japan, the FRG, etc., is presented and the technical pre-requisites for the use of nuclear power in metallurgy, namely the use of high temperature reactors and their incorporation in nuclear metallurgical complexes are discussed. The problems are indicated of the selection of suitable materials for high temperature reactors and the experience is described with the operation of such equipment. The results are given of the analysis of 10 variants of the model of a nuclear metallurgical complex manufacturing 1000 tons of sponge iron per day and having four main technological circuits (the helium circuit, the steam circuit, the reduction gas circuit and the cycle of metallurgical processes). An estimate is given of the capital costs of building a high temperature reactor, a power plant and a metallurgical complex with the reactor. The costs are also given of steel and power production in a nuclear metallurgical complex.

Comparative Analysis of Hydrogen Production Methods with Nuclear Reactors

International Nuclear Information System (INIS)

Morozov, Andrey

2008-01-01

Hydrogen is highly effective and ecologically clean fuel. It can be produced by a variety of methods. Presently the most common are through electrolysis of water and through the steam reforming of natural gas. It is evident that the leading method for the future production of hydrogen is nuclear energy. Several types of reactors are being considered for hydrogen production, and several methods exist to produce hydrogen, including thermochemical cycles and high-temperature electrolysis. In the article the comparative analysis of various hydrogen production methods is submitted. It is considered the possibility of hydrogen production with the nuclear reactors and is proposed implementation of research program in this field at the IPPE sodium-potassium eutectic cooling high temperature experimental facility (VTS rig). (authors)

Economic aspects of radionuclide production for nuclear medicine

International Nuclear Information System (INIS)

Le Gallic, Y.; Prospert, J.

1980-03-01

In a difficult economic situation it was considered advisable to inform users of certain financial aspects of radionuclide production for nuclear medicine. Two aspects of this vast and many-sided problem are developed here: - The cost price structure of different products (radiopharmaceutical and radioimmunological) which defines the size of the market consistent with a balanced budget. This aspect of the economic analysis seems all the more important as ORIS, although a non profit-making organization, has to balance its production costs. - The effects on the national economy of the nuclear medicine supply market. From this viewpoint it seemed interesting to examine the share-out of the French market between ORIS which is practically the only national producer and importers, as well as the balance of payments situation in this respect [fr

Calculation of LUEC using HEEP Software for Nuclear Hydrogen Production Plant

Energy Technology Data Exchange (ETDEWEB)

Kim, Jongho; Lee, Kiyoung; Kim, Minhwan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

To achieve the hydrogen economy, it is very important to produce a massive amount of hydrogen in a clean, safe and efficient way. Nuclear production of hydrogen would allow massive production of hydrogen at economic prices while avoiding environments pollution by reducing the release of carbon dioxide. A Very High Temperature Reactor (VHTR) is considered as an efficient reactor to couple with the thermo-chemical Sulfur Iodine (SI) cycle to achieve the hydrogen economy. HEEP(Hydrogen Economy Evaluation Program) is one of the software tools developed by IAEA to evaluate the economy of the nuclear hydrogen production system by estimating unit hydrogen production cost. In this paper, the LUHC (Levelized Unit Hydrogen Cost) is calculated by using HEEP for nuclear hydrogen production plant, which consists of 4 modules of 600 MWth VHTR coupled with SI process. The levelized unit hydrogen production cost(LUHC) was calculated by the HEEP software.

Relationships between economic and technical research in nuclear power complex

International Nuclear Information System (INIS)

Drahny, M.; Martinek, J.

1984-01-01

The period from projecting and construction to operation and decommissioning of a nuclear power plant spans approximately 5a years. During this period it is necessary to resolve a range of technical, economic and social research problems. Even more complicated is the nuclear power complex as a whole. The respective technical and economic aspects are interactive and cannot be solved separately. It is therefore suggested that the respective national research and development program be linked with the national program of economic research, this both at the preparatory stage, in the course of work and during the evaluation of achieved results. (Ha)

Linking legacies: Connecting the Cold War nuclear weapons production processes to their environmental consequences

International Nuclear Information System (INIS)

1997-01-01

In the aftermath of the Cold War, the US has begun addressing the environmental consequences of five decades of nuclear weapons production. In support of this effort, the National Defense Authorization Act for Fiscal Year 1995 directed the Department of Energy (DOE) to describe the waste streams generated during each step in the production of nuclear weapons. Accordingly, this report responds to this mandate, and it is the Department's first comprehensive analysis of the sources of waste and contamination generated by the production of nuclear weapons. The report also contains information on the missions and functions of nuclear weapons facilities, on the inventories of waste and materials remaining at these facilities, as well as on the extent and characteristics of contamination in and around these facilities. This analysis unites specific environmental impacts of nuclear weapons production with particular production processes. The Department used historical records to connect nuclear weapons production processes with emerging data on waste and contamination. In this way, two of the Department's legacies--nuclear weapons manufacturing and environmental management--have become systematically linked. The goal of this report is to provide Congress, DOE program managers, non-governmental analysts, and the public with an explicit picture of the environmental results of each step in the nuclear weapons production and disposition cycle

Linking legacies: Connecting the Cold War nuclear weapons production processes to their environmental consequences

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-01-01

In the aftermath of the Cold War, the US has begun addressing the environmental consequences of five decades of nuclear weapons production. In support of this effort, the National Defense Authorization Act for Fiscal Year 1995 directed the Department of Energy (DOE) to describe the waste streams generated during each step in the production of nuclear weapons. Accordingly, this report responds to this mandate, and it is the Department`s first comprehensive analysis of the sources of waste and contamination generated by the production of nuclear weapons. The report also contains information on the missions and functions of nuclear weapons facilities, on the inventories of waste and materials remaining at these facilities, as well as on the extent and characteristics of contamination in and around these facilities. This analysis unites specific environmental impacts of nuclear weapons production with particular production processes. The Department used historical records to connect nuclear weapons production processes with emerging data on waste and contamination. In this way, two of the Department`s legacies--nuclear weapons manufacturing and environmental management--have become systematically linked. The goal of this report is to provide Congress, DOE program managers, non-governmental analysts, and the public with an explicit picture of the environmental results of each step in the nuclear weapons production and disposition cycle.

Research on application of complex-genetic algorithm in nuclear component optimal design

International Nuclear Information System (INIS)

He Shijing; Yan Changqi; Wang Jianjun; Wang Meng

2010-01-01

Complex algorithm is one of the most commonly used methods in the mechanical design optimization, such as the optimization of nuclear component. An improved method,complex-genetic algorithm(CGA), is developed based on traditional complex algorithm(TCA), in which the disadvantages of TCA have been overcome. An optimal calculation,which represents the pressurizer, is carried out in order to analyze the optimization capability of CGA. The results show that CGA has better optimizing performance than TCA. (authors)

Nuclear-derived techniques improve cattle productivity and milk quality in Cameroon

International Nuclear Information System (INIS)

Dixit, Aabha

2016-01-01

Increasing agricultural production and improving the quality of milk and meat are key to combating poverty and increasing food security in Africa. Countries such as Cameroon are increasingly turning to innovative, nuclear and nuclear-derived techniques to control and prevent diseases among livestock, and boost cattle and milk production.

Towards the nuclear holocaust. 2. ed.

International Nuclear Information System (INIS)

Ryle, M.

1981-01-01

The subject is discussed under the headings: introduction; nuclear war ((a) the weapons (size, number, type, range); (b) how nuclear war will start (accident or intention, superpowers or others, first strike); (c) the effects of nuclear war); the nuclear industry ((a) nuclear power (relevance to energy needs; alternatives; economics); (b) nuclear weapons (production of Pu)); the military-industrial complex; the USA (US bases in UK and US-UK cooperation); obtaining public support; a return to democracy. (U.K.)

Quantification of effluents in the production of nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Sakai, Mayara C.C.B.; Riella, Humberto G.; Carvalho, Elita F.U. de, E-mail: mcostac@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2017-07-01

At the Instituto de Pesquisa Energéticas e Nucleares (IPEN), the Centro de Combustível Nuclear (CCN), Sao Paulo, SP, Brazil, is responsible for manufacturing fuels for the IEA-R1 reactor and, possibly, the multipurpose reactor fuels. In order to meet the demand for both reactors, the CCN developed a new plant. The production process of the fuel generates several types of effluents - containing uranium or not - being solid, liquid and gaseous with varied physical and chemical characteristics. The objective of this work is to follow the nuclear fuel production process and to identify, quantify and characterize the effluents, especially the liquid ones, to later elaborate a plan of management of these and eventually dispose in a responsible way in the environment. (author)

Quantification of effluents in the production of nuclear fuel

International Nuclear Information System (INIS)

Sakai, Mayara C.C.B.; Riella, Humberto G.; Carvalho, Elita F.U. de

2017-01-01

At the Instituto de Pesquisa Energéticas e Nucleares (IPEN), the Centro de Combustível Nuclear (CCN), Sao Paulo, SP, Brazil, is responsible for manufacturing fuels for the IEA-R1 reactor and, possibly, the multipurpose reactor fuels. In order to meet the demand for both reactors, the CCN developed a new plant. The production process of the fuel generates several types of effluents - containing uranium or not - being solid, liquid and gaseous with varied physical and chemical characteristics. The objective of this work is to follow the nuclear fuel production process and to identify, quantify and characterize the effluents, especially the liquid ones, to later elaborate a plan of management of these and eventually dispose in a responsible way in the environment. (author)

A digital processing method for the analysis of complex nuclear spectra

International Nuclear Information System (INIS)

Madan, V.K.; Abani, M.C.; Bairi, B.R.

1994-01-01

This paper describes a digital processing method using frequency power spectra for the analysis of complex nuclear spectra. The power spectra were estimated by employing modified discrete Fourier transform. The method was applied to observed spectral envelopes. The results for separating closely-spaced doublets in nuclear spectra of low statistical precision compared favorably with those obtained by using a popular peak fitting program SAMPO. The paper also describes limitations of the peak fitting methods. It describes the advantages of digital processing techniques for type II digital signals including nuclear spectra. A compact computer program occupying less than 2.5 kByte of memory space was written in BASIC for the processing of observed spectral envelopes. (orig.)

Nuclear waste management and sustainable development: the complexity of a decision in a controversial universe

International Nuclear Information System (INIS)

Le Dars, A.

2002-01-01

This PhD dissertation intends to demonstrate in what extent the concept of sustainable development applied to nuclear waste management requires a novel scientific approach. High-level and long-lived radioactive waste management needs to make decisions in taking into account multiple dimensions, characterised by uncertainty, irreversibility, and long term, and which are much debated. These scientific controversies often induce social conflicts due to the divergence in stakeholders point of views, values or interests. Therefore, nuclear waste management in a sustainable development constitutes a complex decision-making problem. This thesis focuses on high-level and long-lived radioactive waste management in the French context because this country is confronted with the most severe conflicts. Researches are operating in the 30 December 1991 law framework, and in 2006 a Parliament decision could be made concerning the choice of a long-term nuclear waste management solution. This survey studies in what extent economics can open to other scientific disciplines in using evaluation tools and decision-making procedures which better integrate several conflicting criteria. This work deals with the criticism of the epistemological and methodological foundations of economic evaluation, notably in questioning the realism of its hypothesis, and a qualitative survey directly made close to stakeholders goes deeper into the analysis of their complex relationships. The first part of this thesis puts in evidence the complexity of a sustainable nuclear waste management. Chapter 1 shows that sustainable nuclear waste management is a health and ecological problem irreducible to a technical solution, and Chapter 2 explains why sustainable nuclear waste management constitutes a social choice problem irreducible to an economic evaluation. The second part of this thesis shows that a concerted decision-making process seems to be a good procedure to overcome this complexity. Chapter 3 analyses

Impact of competition on nuclear production

International Nuclear Information System (INIS)

Slade, G.B.

1993-01-01

The Comprehensive National Energy Policy Act of 1992 made access to utility transmission systems by Independent other utilities, and wholesale generators easier and cheaper. Further, the law requires that transmission rates be set to allow recovery of only legitimate and verifiable costs. According to Douglas Smith in the January 1993 issue of Power Engineering, non-utility generators of electricity increased installed capacity by 16% from 1989 to 1990. During that same period, regulated utilities added only 1% of new capacity. By 1993 non-utility generation is expected to supply 62,000 Megawatts of U.S. electric power. It is likely that with the transmission barrier to entry decreased, the non-utility generators will continue to expand even faster. Recent rulings by several public service commissions have put utilities on-notice that future additions to capacity will have to be demonstrated to be the most cost-effective method to serve customers' needs. In the nuclear production part of the business, the author has already started to see some impact from this increased competition: Trojan, Yankee Rowe, San Onofre-1, and Rancho Seco, have either shut down or have announced their imminent shutdown as a result of economic concerns. The paper presents ten years of operating and maintenance costs taken from Utility Data Institute reports of data reported to the Federal Energy Regulatory Commission (FERC) by the utilities who operate the nuclear and fossil production facilities in the United States. It is apparent that the non-fuel costs for nuclear plants have increased substantially. This paper examines the impacts of these cost increases on the ability of nuclear plants to compete in an increasingly competitive marketplace

Material science as basis for nuclear medicine: Holmium irradiation for radioisotopes production

Science.gov (United States)

Usman, Ahmed Rufai; Khandaker, Mayeen Uddin; Haba, Hiromitsu; Otuka, Naohiko

2018-05-01

Material Science, being an interdisciplinary field, plays important roles in nuclear science. These applications are seen in weaponry, armoured vehicles, accelerator structure and development, semiconductor detectors, nuclear medicine and many more. Present study presents the applications of some metals in nuclear medicine (radioisotope production). The charged-particle-induced nuclear reactions by using cyclotrons or accelerators have become a very vital feature of the modern nuclear medicine. Realising the importance of excitation functions for the efficient production of medical radionuclides, some very high purity holmium metals are generally prepared or purchased for bombardment in nuclear accelerators. In the present work, various methods to obtain pure holmium for radioisotope production have been discussed while also presenting details of our present studies. From the experimental work of the present studies, some very high purity holmium foils have been used in the work for a comprehensive study of residual radionuclides production cross-sections. The study was performed using a stacked-foil activation technique combined with γ-ray spectrometry. The stack was bombarded with 50.4 MeV alpha particle beam from AVF cyclotron of RI Beam Factory, Nishina Centre for Accelerator-Based Science, RIKEN, Japan. The work produced thulium radionuclides useful in nuclear medicine.

Production of nuclear graphite in France

International Nuclear Information System (INIS)

Legendre, P.; Mondet, L.; Arragon, Ph.; Cornuault, P.; Gueron, J.; Hering, H.

1955-01-01

The graphite intended for the construction of the reactors is obtained by the usual process: confection of a cake from coke of oil and tar, cooked (in a electric oven) then the product of cook is graphitized, also by electric heating. The use of the air transportation and the control of conditions cooking and graphitization have permitted to increase the nuclear graphite production as well as to better control their physical and mechanical properties and to reduce to the minimum the unwanted stains. (M.B.) [fr

Economic efficiency of Nuclear Cell Mars with reference to different regions with the account cogenerating production

International Nuclear Information System (INIS)

Alekseev, P. N.; Kucharkin, N. E.; Udjanskiy, Y. N.; Schepetina, T. D.; Subbotin, S. A.

2004-01-01

The popular belief in a low economic efficiency NPP with nuclear reactors of small capacity (SNPP) is stipulated by the stereotyped approach to their role as a power source (PS) and absence of a system approach to an estimation of their role and place in economy of regions. Actually, the specific expenses of installed capacity for SNPP can be some times higher than those for ones with high-power reactors. As a rule, pay back of the SNPP projects is justified proceeding from only the income of sale produced electric power and heat. Poor economic efficiency of such variant of use forces the developers to consider variants cogeneration of useful production, for example, power-desalination complexes. But thus it is not taken into account, that only nuclear power source (NPS), due to quality of long-term autonomy can ensure in hard-to-reach regions ecologically safe, practically unbounded on time, reliable energy provision of unique production manufacture, which can be yielded only in a sectional place and due to presence of reliable and ecologically acceptable power supply. Examples of such exclusive symbiosis of technologies can be enough, especially taking into account the factor of an ecological acceptability, which acquires the increasing weight at definition of competitiveness of the projects. The factor of uniqueness at technologies combination in a sectional context does not contradict the strategy of seriality small capacity NPS application, as they are irreplaceable for long-time and reliable power supply of the independent removed or hard-to-reach consumers. In this their special applicability and their specific energy niche, which not busy while by any another PS. On land their role is similar nuclear submarines, which thanking NPS have got completely other quality of autonomy in the discharge of underwater kettles.The territory of Russia on the area both variety of resources and manufactures allows to implement different variants and combinations of

Spent nuclear fuel project product specification

International Nuclear Information System (INIS)

PAJUNEN, A.L.

1999-01-01

This document establishes the limits and controls for the significant parameters that could potentially affect the safety and/or quality of the Spent Nuclear Fuel (SNF) packaged for processing, transport, and storage. The product specifications in this document cover the SNF packaged in Multi-Canister Overpacks to be transported throughout the SNF Project

Legal aspects of nuclear power production and utilization in the USSR

International Nuclear Information System (INIS)

Iojrysh, A.I.; Supataeva, O.A.

1986-01-01

The history and prospects of development of nuclear power engineering in the USSR are considered. The problems of establishment and development of the atomic energy law are discussed. The general characteristics of the atomic energy legislation are given. The principal problem of the atomic energy law is the development of the mechanism fo nuclear power engineering management able to provide protection of people life, health and property. Peaceful use of nuclear energy is the basic principle of the Soviet atomic energy law. Departamental acts are the main sources of atomic energy legislation. Ordering of legislation, its systematization, approval of a complex standard act being the Soviet atomic energy law will result in completing the formation of a new complex branch of soviet legislation namely, the atomic energy law

Production logistic for an attack nuclear submarine squadron fuel

International Nuclear Information System (INIS)

Guimaraes, Leonam dos Santos

1999-01-01

The future acquisition of nuclear attack submarines by Brazilian Navy along next century will imply new requirements on Naval Logistic Support System. These needs will impact all the six logistic functions. Among them, fuel supply could be considered as the one which requires the most important capacitating effort, including not only technological development of processes but also the development of a national industrial basis for effective production of nuclear fuel. This paper presents the technical aspects of the processes involved and an annual production dimensioning for an squadron composed by four units. (author)

13C nuclear magnetic resonance study of the complexation of calcium by taurine

International Nuclear Information System (INIS)

Irving, C.S.; Hammer, B.E.; Danyluk, S.S.; Klein, P.D.

1980-01-01

13 C Nuclear magnetic resonance chemical shifts, 1 J/sub c-c/ scalar coupling constants, spin-lattice relaxation times, and nuclear Overhauser effects were determined for taurine-[1, 2 13 C] and a taurine-[1 13 C] and taurine-[2 13 C] mixture in the presence and absence of calcium. Comparison of taurine titration shifts to values for related compounds reveals some unusual electronic properties of the taurine molecule. Stability constants of 1:1 calcium complexes with taurine zwitterions and anions, as well as their 13 C chemical shifts, were obtained by least squares analysis of titration curves measured in the presence of calcium. The stability constants of calcium-taurine complexes were significantly lower than previous values and led to estimates that only approximately one percent of intracellular calcium of mammalian myocardial cells would exist in a taurine complex

AFM visualization of sub-50nm polyplex disposition to the nuclear pore complex without compromising the integrity of the nuclear envelope

DEFF Research Database (Denmark)

Andersen, Helene; Parhamifar, Ladan; Hunter, A Christy

2016-01-01

that were microinjected into the oocytes of Xenopus laevis, as an example of a non-dividing cell, is exclusive to the nuclear pore complex (NPC). AFM images show NPCs clogged only with sub-50nm polyplexes. This mode of disposition neither altered the morphology/integrity of the nuclear membrane nor the NPC...

Notice to exporters on products prohibited from export (nuclear material, equipment and large nuclear units)

International Nuclear Information System (INIS)

1988-01-01

In order to ensure that the policy to avoid the proliferation of nuclear weapons is complied with, the French Administration applies stricter controls over the export of certain sensitive products, materials and equipment. To this effect, lists of such products, materials and equipment are published in the form of Notices to exporters and periodically revised. This Notice repeals and replaces the previous Notice published in the Official Gazette of 21 January 1986. Annex I contains the list of materials whose export is subject to nuclear non-proliferation controls. Annex II lists the equipment whose export is subject to the same controls. Annex III includes the list of large nuclear units for which an application for prior approval of export must be submitted to the Administrations concerned. (NEA) [fr

Design principles of nuclear receptor signaling: how complex networking improves signal transduction

Science.gov (United States)

Kolodkin, Alexey N; Bruggeman, Frank J; Plant, Nick; Moné, Martijn J; Bakker, Barbara M; Campbell, Moray J; van Leeuwen, Johannes P T M; Carlberg, Carsten; Snoep, Jacky L; Westerhoff, Hans V

2010-01-01

The topology of nuclear receptor (NR) signaling is captured in a systems biological graphical notation. This enables us to identify a number of ‘design' aspects of the topology of these networks that might appear unnecessarily complex or even functionally paradoxical. In realistic kinetic models of increasing complexity, calculations show how these features correspond to potentially important design principles, e.g.: (i) cytosolic ‘nuclear' receptor may shuttle signal molecules to the nucleus, (ii) the active export of NRs may ensure that there is sufficient receptor protein to capture ligand at the cytoplasmic membrane, (iii) a three conveyor belts design dissipating GTP-free energy, greatly aids response, (iv) the active export of importins may prevent sequestration of NRs by importins in the nucleus and (v) the unspecific nature of the nuclear pore may ensure signal-flux robustness. In addition, the models developed are suitable for implementation in specific cases of NR-mediated signaling, to predict individual receptor functions and differential sensitivity toward physiological and pharmacological ligands. PMID:21179018

Hydrogen Production from Nuclear Energy

Science.gov (United States)

Walters, Leon; Wade, Dave

2003-07-01

During the past decade the interest in hydrogen as transportation fuel has greatly escalated. This heighten interest is partly related to concerns surrounding local and regional air pollution from the combustion of fossil fuels along with carbon dioxide emissions adding to the enhanced greenhouse effect. More recently there has been a great sensitivity to the vulnerability of our oil supply. Thus, energy security and environmental concerns have driven the interest in hydrogen as the clean and secure alternative to fossil fuels. Remarkable advances in fuel-cell technology have made hydrogen fueled transportation a near-term possibility. However, copious quantities of hydrogen must be generated in a manner independent of fossil fuels if environmental benefits and energy security are to be achieved. The renewable technologies, wind, solar, and geothermal, although important contributors, simply do not comprise the energy density required to deliver enough hydrogen to displace much of the fossil transportation fuels. Nuclear energy is the only primary energy source that can generate enough hydrogen in an energy secure and environmentally benign fashion. Methods of production of hydrogen from nuclear energy, the relative cost of hydrogen, and possible transition schemes to a nuclear-hydrogen economy will be presented.

MODERN TOOLS OF PRODUCT PROMOTION OF MILITARY-INDUSTRIAL COMPLEX

OpenAIRE

Tuliakova, I. R.; Chesnokova, M.S.

2014-01-01

This article is devoted to the promotion of production of the military-industrial complex. In the new economy require specially coordinated effort to promote products, was no exception and the military-industrial complex. The article notes that the way can be used as tools of industrial marketing, marketing tools and experience.

Oil sand synfuel production using nuclear energy

International Nuclear Information System (INIS)

Barnert, H.

1984-10-01

The importance of oil sand as a primary energy carrier is illustrated. The oil sand mining project 'synfuel' in Fort McMurray, Alberta, Canada, is described. On the basis of a layout of an In-situ-process different possibilities of introducing nuclear energy to the process are described. This leads to an increase of the product yield, leading finally to a doubling of the energy output compared to the reference layout. The introduction of nuclear energy contributes to the reduction of emissions, in particular to the emission of carbon dioxide in the conversion process. (orig.)

Macrocyclic complexes of radionuclides in nuclear medicine

International Nuclear Information System (INIS)

Majkowska, A.; Bilewicz, A.

2008-01-01

The use of radiometal-labeled small complexes and biomolecules as diagnostic and therapeutic agents is a relatively new area of medical research. Radiopharmaceuticals are radiolabeled molecules designed to deliver ionizing radiation doses to specific disease sites. Between the targeting biomolecule and a radionuclide a bifunctional ligand is inserted, one end of which is covalently attached to the targeting molecule either directly or through a linker whereas the other strongly coordinates a metallic radionuclide. Selection of a bifunctional ligand is largely determined by the nature and oxidation state of a metal ion. The metal chelate can significantly affect the tumor uptake and biodistribution of radiopharmaceuticals based on small biomolecules. This is because in many cases the metal chelate contributes greatly to the overall size and lipophilicity of the radiopharmaceutical. Therefore, the design and selection of the ligand is very important for the development of a clinically useful therapeutic agent. The requirement for high thermodynamic and kinetic stability of the metal complex is often achieved through the use of macrocyclic ligands with a functionalized arm for covalent bonding to the biomolecule. In this review synthesis of bifunctional macrocyclic ligands and properties of radionuclide macrocyclic complexes used in nuclear medicine are presented. We describe results in two areas: substituted macrocyclic aza ligands for chelation of hard metal cations, and macrocycles containing sulphur for complexation of soft metal cations. Special attention was paid to stability of the complexes as well as to their lipophilicity, which affect biological properties of the formed radiopharmaceuticals. We also include a forecast of the near-term opportunities that are likely to determine practice in the next few years. (authors)

Glutarimidedioxime. A complexing and reducing reagent for plutonium recovery from spent nuclear fuel reprocessing

Energy Technology Data Exchange (ETDEWEB)

Xian, Liang [China Institute of Atomic Energy, Beijing (China). Radiochemistry Dept.; Tian, Guoxin [China Institute of Atomic Energy, Beijing (China). Radiochemistry Dept.; Lawrence Berkeley National Laboratory, Berkeley, CA (United States). Chemical Sciences Div.; Beavers, Christine M.; Teat, Simon J. [Lawrence Berkeley National Laboratory, Berkeley, CA (United States). Advanced Light Source; Shuh, David K. [Lawrence Berkeley National Laboratory, Berkeley, CA (United States). Chemical Sciences Div.

2016-04-04

Efficient separation processes for recovering uranium and plutonium from spent nuclear fuel are essential to the development of advanced nuclear fuel cycles. The performance characteristics of a new salt-free complexing and reducing reagent, glutarimidedioxime (H{sub 2}A), are reported for recovering plutonium in a PUREX process. With a phase ratio of organic to aqueous of up to 10:1, plutonium can be effectively stripped from 30 % tributyl phosphate (TBP) in kerosene into 1M HNO{sub 3} with H{sub 2}A. The complexation-reduction mechanism is illustrated with the combination of UV/Vis absorption spectra and the crystal structure of a Pu{sup IV} complex with the reagent. The fast stripping rate and the high efficiency for stripping Pu{sup IV}, through the complexation-reduction mechanism, is suitable for use in centrifugal contactors with very short contact/resident times, thereby offering significant advantages over conventional processes.

Nuclear hydrogen production and its safe handling

International Nuclear Information System (INIS)

Chung, Hongsuk; Paek, Seungwoo; Kim, Kwang-Rag; Ahn, Do-Hee; Lee, Minsoo; Chang, Jong Hwa

2003-01-01

An overview of the hydrogen related research presently undertaken at the Korea Atomic Energy Research Institute are presented. These encompass nuclear hydrogen production, hydrogen storage, and the safe handling of hydrogen, High temperature gas-cooled reactors can play a significant role, with respect to large-scale hydrogen production, if used as the provider of high temperature heat in fossil fuel conversion or thermochemical cycles. A variety of potential hydrogen production methods for high temperature gas-cooled reactors were analyzed. They are steam reforming of natural gas, thermochemical cycles, etc. The produced hydrogen should be stored safely. Titanium metal was tested primarily because its hydride has very low dissociation pressures at normal storage temperatures and a high capacity for hydrogen, it is easy to prepare and is non-reactive with air in the expected storage conditions. There could be a number of potential sources of hydrogen evolution risk in a nuclear hydrogen production facility. In order to reduce the deflagration detonation it is necessary to develop hydrogen control methods that are capable of dealing with the hydrogen release rate. A series of experiments were conducted to assess the catalytic recombination characteristics of hydrogen in an air stream using palladium catalysts. (author)

Nuclear disarmament verification

International Nuclear Information System (INIS)

DeVolpi, A.

1993-01-01

Arms control treaties, unilateral actions, and cooperative activities -- reflecting the defusing of East-West tensions -- are causing nuclear weapons to be disarmed and dismantled worldwide. In order to provide for future reductions and to build confidence in the permanency of this disarmament, verification procedures and technologies would play an important role. This paper outlines arms-control objectives, treaty organization, and actions that could be undertaken. For the purposes of this Workshop on Verification, nuclear disarmament has been divided into five topical subareas: Converting nuclear-weapons production complexes, Eliminating and monitoring nuclear-weapons delivery systems, Disabling and destroying nuclear warheads, Demilitarizing or non-military utilization of special nuclear materials, and Inhibiting nuclear arms in non-nuclear-weapons states. This paper concludes with an overview of potential methods for verification

High energy gamma-ray production in nuclear reactions

International Nuclear Information System (INIS)

Pinston, J.A.; Nifenecker, H.; Nifenecker, H.

1989-01-01

Experimental techniques used to study high energy gamma-ray production in nuclear reactions are reviewed. High energy photon production in nucleus-nucleus collisions is discussed. Semi-classical descriptions of the nucleus-nucleus gamma reactions are introduced. Nucleon-nucleon gamma cross sections are considered, including theoretical aspects and experimental data. High energy gamma ray production in proton-nucleus reactions is explained. Theoretical explanations of photon emission in nucleus-nucleus collisions are treated. The contribution of charged pion currents to photon production is mentioned

Development of the nuclear weapons complex EP architecture

Energy Technology Data Exchange (ETDEWEB)

Murray, C.; Halbleib, L.

1996-07-01

The Nuclear Weapons Guidance Team is an interagency committee led by Earl Whiteman, DOE that chartered the generation of EP40100, Concurrent Qualification and its successor EP401099, Concurrent Engineering and Qualification. As this new philosophy of concurrent operations has evolved and as implementation has been initiated, conflicts and insufficiencies in the remaining Engineering Procedures (EPs) have become more apparent. At the Guidance Team meeting in November 1995, this issue was explored and several approaches were considered. It was concluded at this meeting, that a smaller set of interagency EPs described in a hierarchical system could provide the necessary interagency direction to support complex-wide implementation. This set consolidates many existing EP processes where consistency and commonality are critical to success of the extended enterprise. The Guidance Team subsequently chartered an interagency team to initiate development activity associated with the envisioned new EP set. This team had participation from seven Nuclear Weapons Complex (NWC) sites as well as DOE/AL and DP-14 (team members are acknowledged later in this report). Per the Guidance Team, this team, referred to as the Architecture Subcommittee, was to map out and define an EP Architecture for the interagency EPs, make recommendations regarding a more agile process for EP approval and suggest an aggressive timeline to develop the combined EPs. The Architecture Subcommittee was asked to brief their output at the February Guidance Team meeting. This SAND report documents the results of the Architecture Subcommittee`s recommendations.

Recovery of sodium hydroxide and silica from zirconium oxide plant effluent of Nuclear Fuel Complex

International Nuclear Information System (INIS)

Bajpai, M.B.; Shenoi, M.R.K.; Keni, V.S.

1994-01-01

Sodium hydroxide (lye) and silica can be recovered in pure form from the alkaline sodium silicate waste of Nuclear Fuel Complex, Hyderabad. Electrolytic method was used to amalgamate the sodium present in an electrolyser with flowing mercury as cathode and nickel as anode. The amalgam is then denuded with water in a graphite packed tower to recover mercury for recycling to the electrolyser and sodium hydroxide lye. Sodium hydroxide lye can be recycled in the zirconium oxide plant. Silica is recovered from the spent electrolyte by ion exchange method using cation exchange resin. Both the process details are described in this paper, with experimental data useful for the scale up. The process converts waste to value products. (author)

Production of nuclear ceramic fuel for nuclear power plants at 'Ulba metallurgical plant' OSC

International Nuclear Information System (INIS)

Khadeev, V.G.

2000-01-01

The paper describes the flow-sheet of production of uranium dioxide powders and nuclear ceramic fuel pellets of them existing at the facility. 'UMP' OSC applies ADU extraction process of UO2 powders production. An indisputable success of the process is the possibility of use of the wide range of raw materials. Uranium hexafluoride, uranium oxides, uranium metal, uranium tetrafluoride, uranyl salts, uranium ore concentrates, all possible types of uranium-containing materials the processing of which by routine methods is difficult (ashes, scraps, etc.) are used as the raw materials. In addition, a reprocessed nuclear fuel can be used for fuel production. The quality of uranium dioxide powder produced does not depend on the type of uranium raw material used. High selectivity of extraction refining makes possible to obtain material with rather low impurities content that meets practically all specifications for uranium dioxide known to us. Ceramic and process features of uranium dioxide powders, namely, specific surface, bulk density, grain size and sinterability make possible to produce nuclear ceramic fuel with specified features. Quality of uranium dioxide powders produced by 'UMP' OSC was highly rated by General Electric company that is one of the leading companies from fuel manufactures in the USA market . It has certified 'UMP' OSC as its supplier. Currently, our company makes great efforts on establishing production of uranium dioxide powders with natural isotopes content for production of fuel for CANDU reactors. Trial lots of such powders are under tests at some companies manufacturing fuel for this type reactors in Canada, USA and Corea

Nuclear power in Russia: status, problems, prospects

International Nuclear Information System (INIS)

Ponomarev-Stepnoy, N.

1992-01-01

To solve the problem of atomic bomb, a powerful nuclear industrial complex has been established in the Soviet Union. This complex has developed a high scientific and engineering potential and enlisted the best science and engineering experts. Strict administration, rigid discipline in execution and operation, to secrecy limiting both internal and external interactions were typical of the complex which presented a state within the state with the inside divide by rigid barriers and protected from the outside by iron curtain. When the atomic bomb was designed and tested the search for a field of application for the nuclear potential available was started: nuclear power plants, nuclear power facilities for submarines and ships, nuclear aircraft and rocket engines, space nuclear facilities. Such were the conditions of forming the nuclear power in USSR. But this nuclear military complex has failed to prevent the Chelyabinsk accident which involved considerable radiological effects. The national industry could not adopt quickly the work style established in a nuclear complex and relative high technologies because of low educational and technical level and poor technological discipline. The results are known: the Chernobyl accident coincided in time with the beginning of the reconstruction of the System, the result of which was this accident. This paper describes the current status of the nuclear park, shows the problems of safety, maintenance, retrofitting, reconstruction or decommissioning. Statistical data on nuclear power in the power production program are also given

World Nuclear University School of Uranium Production: Eight years' experience

International Nuclear Information System (INIS)

Trojacek, J.

2014-01-01

The World Nuclear University School of Uranium Production was established by DIAMO, state enterprise in 2006 year under the auspices of the World Nuclear University in London in partnership with international nuclear organizations – OECD/NEA and IAEA. Using the expertise and infrastructure of DIAMO State Enterprise, in conjuction with national and international universities, scientific institutions, regulatory authorities and other individual experts, the “school” covers its mission with the aim to provide world-class training on all aspects of uranium production cycle to equip operators, regulators and executives with the knowledge and expertise needed to provide expanded, environmentally-sound uranium mining throughout the world: • to educate students on all aspects of uranium production cycle including exploration, planning, development, operation, remediation and closure of uranium production facilities; • to improve the state of the art of uranium exploration, mining and mine remediation through research and development; • to provide a forum for the exchange of information on the latest uranium mining technologies and experiences – best practices.

Criteria for the design of the control room complex for a nuclear power generating station

International Nuclear Information System (INIS)

Anon.

1981-01-01

This Standard addresses the central control room of a nuclear power generating station and the overall complex in which this room is housed. It is not intended to cover special or normally unattended control rooms, such as those provided for radioactive waste handling or for emergency shutdown operations. The nuclear power generating station control room complex provides a protective envelope for plant operating personnel and for instrument and control equipment vital to the operation of the plant during normal and abnormal conditions. In this capacity, the control room complex must be designed and constructed to meet the following criteria contained in Appendix A of 10CFR50, General Design criteria for Nuclear Power Plants: (1) Criterion 2: design bases for protection against natural phenomena; (2) Criterion 3: fire protection; (3) Criterion 4: environmental and missile design bases; (4) Criterion 5: sharing of structures, systems and components (multiunit stations only); and (5) Criterion 19: control room

SUBSTANTIATION OF SOLUTIONS PERTAINING TO COMPLEX PRODUCTION RECONSTRUCTION

Directory of Open Access Journals (Sweden)

V. Y. Gurinovich

2011-01-01

Full Text Available While taking an example of reconstruction and modernization of OJSC «Construction and Mounting Trust No.16, Novopolotsk» the paper substantiates solutions for complex production reconstruction. The production reconstruction is divided in three start-up facilities ensuring continuous finished-product output.

Development of the complex of nuclear-physical methods of analysis for geology and technology tasks in Kazakhstan

International Nuclear Information System (INIS)

Solodukhin, V.; Silachyov, I.; Poznyak, V.; Gorlachev, I.

2016-01-01

The paper describes the development of nuclear-physical methods of analysis and their applications in Kazakhstan for geological tasks and technology. The basic methods of this complex include instrumental neutron-activation analysis, x-ray fluorescent analysis and instrumental γ-spectrometry. The following aspects are discussed: applications of developed and adopted analytical techniques for assessment and calculations of rare-earth metal reserves at various deposits in Kazakhstan, for technology development of mining and extraction from uranium-phosphorous ore and wastes, for radioactive coal gasification technology, for studies of rare metal contents in chromite, bauxites, black shales and their processing products. (author)

Underground nuclear energy complexes - technical and economic advantages

Energy Technology Data Exchange (ETDEWEB)

Myers, Carl W [Los Alamos National Laboratory; Kunze, Jay F [IDAHO STATE UNIV; Giraud, Kellen M [BABECOCK AND WILCOX; Mahar, James M [IDAHO STATE UNIV

2010-01-01

Underground nuclear power plant parks have been projected to be economically feasible compared to above ground instalIations. This paper includes a thorough cost analysis of the savings, compared to above ground facilities, resulting from in-place entombment (decommissioning) of facilities at the end of their life. reduced costs of security for the lifetime of the various facilities in the underground park. reduced transportation costs. and reduced costs in the operation of the waste storage complex (also underground). compared to the fair share of the costs of operating a national waste repository.

Applications of nuclear data on short-lived fission products

International Nuclear Information System (INIS)

Rudstam, G.; Aagaard, P.; Aleklett, K.; Lund, E.

1981-01-01

The study of short-lived fission products gives information about the nuclear structure on the neutron-rich side of stability. The data are also of interest for various applications both to basic science and to nuclear technology. Some of these applications, taken up by the OSIRIS group at Studsvik, are described in the present contribution. (orig.)

Three-Dimensional Mapping of mRNA Export through the Nuclear Pore Complex

Directory of Open Access Journals (Sweden)

Steven J. Schnell

2014-11-01

Full Text Available The locations of transcription and translation of mRNA in eukaryotic cells are spatially separated by the nuclear envelope (NE. Plenty of nuclear pore complexes (NPCs embedded in the NE function as the major gateway for the export of transcribed mRNAs from the nucleus to the cytoplasm. Whereas the NPC, perhaps one of the largest protein complexes, provides a relatively large channel for macromolecules to selectively pass through it in inherently three-dimensional (3D movements, this channel is nonetheless below the diffraction limit of conventional light microscopy. A full understanding of the mRNA export mechanism urgently requires real-time mapping of the 3D dynamics of mRNA in the NPC of live cells with innovative imaging techniques breaking the diffraction limit of conventional light microscopy. Recently, super-resolution fluorescence microscopy and single-particle tracking (SPT techniques have been applied to the study of nuclear export of mRNA in live cells. In this review, we emphasize the necessity of 3D mapping techniques in the study of mRNA export, briefly summarize the feasibility of current 3D imaging approaches, and highlight the new features of mRNA nuclear export elucidated with a newly developed 3D imaging approach combining SPT-based super-resolution imaging and 2D-to-3D deconvolution algorithms.

How the nucleus and mitochondria communicate in energy production during stress: nuclear MtATP6, an early-stress responsive gene, regulates the mitochondrial F₁F₀-ATP synthase complex.

Science.gov (United States)

Moghadam, Ali Asghar; Ebrahimie, Eemaeil; Taghavi, Seyed Mohsen; Niazi, Ali; Babgohari, Mahbobeh Zamani; Deihimi, Tahereh; Djavaheri, Mohammad; Ramezani, Amin

2013-07-01

A small number of stress-responsive genes, such as those of the mitochondrial F1F0-ATP synthase complex, are encoded by both the nucleus and mitochondria. The regulatory mechanism of these joint products is mysterious. The expression of 6-kDa subunit (MtATP6), a relatively uncharacterized nucleus-encoded subunit of F0 part, was measured during salinity stress in salt-tolerant and salt-sensitive cultivated wheat genotypes, as well as in the wild wheat genotypes, Triticum and Aegilops using qRT-PCR. The MtATP6 expression was suddenly induced 3 h after NaCl treatment in all genotypes, indicating an early inducible stress-responsive behavior. Promoter analysis showed that the MtATP6 promoter includes cis-acting elements such as ABRE, MYC, MYB, GTLs, and W-boxes, suggesting a role for this gene in abscisic acid-mediated signaling, energy metabolism, and stress response. It seems that 6-kDa subunit, as an early response gene and nuclear regulatory factor, translocates to mitochondria and completes the F1F0-ATP synthase complex to enhance ATP production and maintain ion homeostasis under stress conditions. These communications between nucleus and mitochondria are required for inducing mitochondrial responses to stress pathways. Dual targeting of 6-kDa subunit may comprise as a mean of inter-organelle communication and save energy for the cell. Interestingly, MtATP6 showed higher and longer expression in the salt-tolerant wheat and the wild genotypes compared to the salt-sensitive genotype. Apparently, salt-sensitive genotypes have lower ATP production efficiency and weaker energy management than wild genotypes; a stress tolerance mechanism that has not been transferred to cultivated genotypes.

Glutarimidedioxime: a complexing and reducing reagent for plutonium recovery from spent nuclear fuel reprocessing

Energy Technology Data Exchange (ETDEWEB)

Xian, Liang [Radiochemistry Department, China Institute of Atomic Energy, Beijing (China); Tian, Guoxin [Radiochemistry Department, China Institute of Atomic Energy, Beijing (China); Chemical Sciences Division, Lawrence Berkeley National Laboratory, Berkeley, CA (United States); Beavers, Christine M.; Teat, Simon J. [Advanced Light Source, Lawrence Berkeley National Laboratory, Berkeley, CA (United States); Shuh, David K. [Chemical Sciences Division, Lawrence Berkeley National Laboratory, Berkeley, CA (United States)

2016-04-04

Efficient separation processes for recovering uranium and plutonium from spent nuclear fuel are essential to the development of advanced nuclear fuel cycles. The performance characteristics of a new salt-free complexing and reducing reagent, glutarimidedioxime (H{sub 2}A), are reported for recovering plutonium in a PUREX process. With a phase ratio of organic to aqueous of up to 10:1, plutonium can be effectively stripped from 30 % tributyl phosphate (TBP) in kerosene into 1 m HNO{sub 3} with H{sub 2}A. The complexation-reduction mechanism is illustrated with the combination of UV/Vis absorption spectra and the crystal structure of a Pu{sup IV} complex with the reagent. The fast stripping rate and the high efficiency for stripping Pu{sup IV}, through the complexation-reduction mechanism, is suitable for use in centrifugal contactors with very short contact/resident times, thereby offering significant advantages over conventional processes. (copyright 2016 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

High-Resolution Imaging Reveals New Features of Nuclear Export of mRNA through the Nuclear Pore Complexes

Directory of Open Access Journals (Sweden)

Joseph M. Kelich

2014-08-01

Full Text Available The nuclear envelope (NE of eukaryotic cells provides a physical barrier for messenger RNA (mRNA and the associated proteins (mRNPs traveling from sites of transcription in the nucleus to locations of translation processing in the cytoplasm. Nuclear pore complexes (NPCs embedded in the NE serve as a dominant gateway for nuclear export of mRNA. However, the fundamental characterization of export dynamics of mRNPs through the NPC has been hindered by several technical limits. First, the size of NPC that is barely below the diffraction limit of conventional light microscopy requires a super-resolution microscopy imaging approach. Next, the fast transit of mRNPs through the NPC further demands a high temporal resolution by the imaging approach. Finally, the inherent three-dimensional (3D movements of mRNPs through the NPC demand the method to provide a 3D mapping of both transport kinetics and transport pathways of mRNPs. This review will highlight the recently developed super-resolution imaging techniques advanced from 1D to 3D for nuclear export of mRNPs and summarize the new features in the dynamic nuclear export process of mRNPs revealed from these technical advances.

Once-through hybrid sulfur process for nuclear hydrogen production

International Nuclear Information System (INIS)

Jeong, Y. H.

2008-01-01

Increasing concern about the global climate change spurs the development of low- or zero-carbon energy system. Nuclear hydrogen production by water electrolysis would be the one of the short-term solutions, but low efficiency and high production cost (high energy consumption) is the technical hurdle to be removed. In this paper the once-through sulfur process composed of the desulfurization and the water electrolysis systems is proposed. Electrode potential for the conventional water electrolysis (∼2.0 V) can be reduced significantly by the anode depolarization using sulfur dioxide: down to 0.6 V depending on the current density This depolarized electrolysis is the electrolysis step of the hybrid sulfur process originally proposed by the Westinghouse. However; recycling of sulfur dioxide requires a high temperature heat source and thus put another technical hurdle on the way to nuclear hydrogen production: the development of high temperature nuclear reactors and corresponding sulfuric acid decomposition system. By the once-through use of sulfur dioxide rather than the closed recycle, the hurdle can be removed. For the sulfur feed, the desulfurization system is integrated into the water electrolysis system. Fossil fuels include a few percent of sulfur by weight. During the refinement or energy conversion, most of the sulfur should be separated The separated sulfur can be fed to the water electrolysis system and the final product would be hydrogen and sulfuric acid, which is number one chemical in the world by volume. Lowered electrode potential and additional byproduct, the sulfuric acid, can provide economically affordable hydrogen. In this study, the once-through hybrid sulfur process for hydrogen production was proposed and the process was optimized considering energy consumption in electrolysis and sulfuric acid concentration. Economic feasibility of the proposed process was also discussed. Based on currently available experimental data for the electrode

Nuclear techniques in animal production and health

Energy Technology Data Exchange (ETDEWEB)

Moustgaard, J [Institute of Physiology, Endocrinology and Bloodgrouping, The Royal Veterinary and Agricultural University, Copenhagen (Denmark)

1976-07-01

In the fight against animal diseases, especially parasitic infections, nuclear techniques have also proved to be of great value, namely in the production of irradiated vaccines against helminthic diseases. In this context it should be stressed that reduced productivity due to protein loss caused by intestinal parasites is a problem of paramount economic importance in developing as well as developed countries. Recently radioisotopes in the so-called radioimmunoassays have also been applied in determination of the hormonal status of farm animals and to elucidate its relation to the environment and to the physiological and nutritional condition of the animal. This rapidly developing technique may make it possible to control the reproductive performance of cattle and sheep more efficiently than has hitherto been the case. Production of animal protein of a high biological value for human nutrition is still a problem of great concern for the less developed countries. Without doubt the use of nuclear techniques, hand in hand with other research methods, will be of great help in overcoming this condition, always provided that the countries in question possess the necessary equipment and trained personnel.

Nuclear techniques in animal production and health

International Nuclear Information System (INIS)

Moustgaard, J.

1976-01-01

In the fight against animal diseases, especially parasitic infections, nuclear techniques have also proved to be of great value, namely in the production of irradiated vaccines against helminthic diseases. In this context it should be stressed that reduced productivity due to protein loss caused by intestinal parasites is a problem of paramount economic importance in developing as well as developed countries. Recently radioisotopes in the so-called radioimmunoassays have also been applied in determination of the hormonal status of farm animals and to elucidate its relation to the environment and to the physiological and nutritional condition of the animal. This rapidly developing technique may make it possible to control the reproductive performance of cattle and sheep more efficiently than has hitherto been the case. Production of animal protein of a high biological value for human nutrition is still a problem of great concern for the less developed countries. Without doubt the use of nuclear techniques, hand in hand with other research methods, will be of great help in overcoming this condition, always provided that the countries in question possess the necessary equipment and trained personnel

Renewal of nuclear electricity production: an economic trend

International Nuclear Information System (INIS)

Debontride, B.; Bouteille, F.; Goebel, A.; Czech, J.

2004-01-01

2004 price evolution on the market asks on nuclear generation profitability and competitiveness. There were over installed capacities in Europe since several years, but electricity consumption is steadily increasing and over capacities will disappear more or less at the end of the decade. On a world basis, electricity demand grows twice as much as energy demand, so that there is a need to invest in new electricity generation capacities. The recent US black out events shows the need for securing energy supply in capacities as well as in transmission and distribution. Competitiveness of the different possible sources of energy thus needs to be carefully assessed by all the worldwide decision makers in the field of power generation. In France, the economy of the electricity production is regularly assessed by a French Government study called 'Reference costs for Electricity production' which compares the levelized cost for base load power produced by a nuclear unit (latest design available) and other conventional power stations. In the latest release published in 2003 the nuclear option (the EPR) is compared with three fossil-fired units: A twin 400 MW combined-cycle gas plant, a twin 900 MW pulverized coal station and a 400 MW fluidized bed combustion coal plant. In all cases the nuclear option is the cheapest. If external costs, based on the EU studies (ExternE), are taken into account, the advantage of the nuclear option is significantly increased. In Finland a study performed by the Lappeenranta University in 2000 concluded also in the competitiveness of the Nuclear option. This result was important in the decision making process which resulted in the decision in principle of the Finnish Parliament to allow for the construction of the fifth Nuclear power station for which the EPR was selected. In China, the same kind of economical studies recently led the governmental authorities to launch new nuclear projects. These three examples, in three countries where

Complex nuclear geophysical methods and apparatus to increase the efficiency of prospecting extracting and processing nonradioactive minerals as examplified by tin ores

International Nuclear Information System (INIS)

Baldin, S.A.; Voloshchuk, S.N.; Egiazarov, B.G.; Zernov, L.V.; Luchin, I.A.; Matveev, V.V.; Pukhal'skij, L.Ch.; Chesnokov, N.I.

1979-01-01

Described is the complex of nuclear geophysical methods and apparatus, with the help of which the problem of the industrial control at all stages of ore concentrating industry are being solved. γ resonance and X-ray radiometric methods and apparatus providing express and not less accurate determination of general tin and tin in the form of cassiterite are used in the complex. The devices developed on the base of semiconductor spectrometers and used both under industrial conditions and in production regimes are used for the first time in the practice of ore concentrating industry. The essential positive effect of the complex on technical economical indices of the industry is found out; it allows to use more effective methods of extracting and processing technology. The similar complexes may be developed for other kinds of nonradioactive minerals

Estimation of the ripple effects on a regional community of the formation of the nuclear energy science complex in Gyeongju

Energy Technology Data Exchange (ETDEWEB)

Lee, Byung-Sik [Dankook Univ., Chungnam (Korea, Republic of). Dept. of Nuclear Engineering; Moon, Joo Hyun [Dongguk Univ. Gyeongju, Gyeongbuk (Korea, Republic of). Dept. of Nuclear Energy Engineering

2017-05-15

Korea has developed advanced nuclear technologies, including those for future nuclear energy systems and the safe management of spent nuclear fuel, and is about to make a decision as to whether to make a massive investment in the development R and D for commercialization of them. There is no area large enough to accommodate all the development R and D-related facilities together at Korea Atomic Energy Research Institute (KAERI) to perform the development R and Ds. KAERI seeks solutions to the space problem, which includes the construction of a nuclear energy science complex (NESC). Gyeongju is one of the potential sites. This study estimated the ripple effects on the regional community if the NESC is to be formed in Gyeongju using inter-regional input-output analysis. The estimation shows that the ripple effects to the regional community of the formation of the NESC in Gyeongju would be 1,086,633 billion Korean Won (KRW) for regional production inducement, 455,299 billion KRW for value-added inducement, and 9,592 persons for employment inducement.

New complex product introduction by means of product configuration

DEFF Research Database (Denmark)

Bonev, Martin; Korell, Manuel; Hvam, Lars

-uct innovation can effectively been supported. Es-pecially for engineering companies moving to-wards Mass Customization, compared to mass pro-ducers the challenges caused by the complexity of their products and by the highly uncertain markets are much higher. This study develops and validates a framework which....... Traditional research has thereby either focused on defining modelling techniques for the configuration model of stable products, on improved configura-tion algorithms, or on the impact of configurators on companies’ operations. However, little attention has yet been paid how the growing need for prod...

New Approach for Nuclear Safety and Regulation - Application of Complexity Theory and System Dynamics

International Nuclear Information System (INIS)

Choi, Kwang Sik; Choi, Young Sung; Han, Kyu Hyun; Kim, Do Hyoung

2007-01-01

The methodology being used today for assuring nuclear safety is based on analytic approaches. In the 21st century, holistic approaches are increasingly used over traditional analytic method that is based on reductionism. Presently, it leads to interest in complexity theory or system dynamics. In this paper, we review global academic trends, social environments, concept of nuclear safety and regulatory frameworks for nuclear safety. We propose a new safety paradigm and also regulatory approach using holistic approach and system dynamics now in fashion

Original theatrical production will explore issues surrounding nuclear power

OpenAIRE

Elliott, Jean

2007-01-01

A new, original theatrical production entitled "Nuclear Power Play" will explore the personal and public politics of nuclear power. Uniquely developed by a team of experts in science and technology working alongside theatre arts practitioners, the play will debut on Wednesday, Nov. 7 at 7:30 p.m. in the Haymarket Theatre at the Squires Student Center on the Virginia Tech campus.

Progress in fission product nuclear data. Issue no. 6

International Nuclear Information System (INIS)

Lammer, G.; Lammer, M.

1980-06-01

This is the sixth issue of a report series on Fission Product Nuclear Data (FPND) which is published by the Nuclear Data Section (NDS) of the International Atomic Energy Agency (IAEA). The purpose of this series is to inform scientists working on FPND, or using such data, about all activities in this field which are planned, ongoing, or have recently been completed

Reprocessing free nuclear fuel production via fusion fission hybrids

Energy Technology Data Exchange (ETDEWEB)

Kotschenreuther, Mike, E-mail: mtk@mail.utexas.edu [Intitute for Fusion Studies, University of Texas at Austin (United States); Valanju, Prashant; Mahajan, Swadesh [Intitute for Fusion Studies, University of Texas at Austin (United States)

2012-05-15

Fusion fission hybrids, driven by a copious source of fusion neutrons can open qualitatively 'new' cycles for transmuting nuclear fertile material into fissile fuel. A totally reprocessing-free (ReFree) Th{sup 232}-U{sup 233} conversion fuel cycle is presented. Virgin fertile fuel rods are exposed to neutrons in the hybrid, and burned in a traditional light water reactor, without ever violating the integrity of the fuel rods. Throughout this cycle (during breeding in the hybrid, transport, as well as burning of the fissile fuel in a water reactor) the fissile fuel remains a part of a bulky, countable, ThO{sub 2} matrix in cladding, protected by the radiation field of all fission products. This highly proliferation-resistant mode of fuel production, as distinct from a reprocessing dominated path via fast breeder reactors (FBR), can bring great acceptability to the enterprise of nuclear fuel production, and insure that scarcity of naturally available U{sup 235} fuel does not throttle expansion of nuclear energy. It also provides a reprocessing free path to energy security for many countries. Ideas and innovations responsible for the creation of a high intensity neutron source are also presented.

Reprocessing free nuclear fuel production via fusion fission hybrids

International Nuclear Information System (INIS)

Kotschenreuther, Mike; Valanju, Prashant; Mahajan, Swadesh

2012-01-01

Fusion fission hybrids, driven by a copious source of fusion neutrons can open qualitatively “new” cycles for transmuting nuclear fertile material into fissile fuel. A totally reprocessing-free (ReFree) Th 232 –U 233 conversion fuel cycle is presented. Virgin fertile fuel rods are exposed to neutrons in the hybrid, and burned in a traditional light water reactor, without ever violating the integrity of the fuel rods. Throughout this cycle (during breeding in the hybrid, transport, as well as burning of the fissile fuel in a water reactor) the fissile fuel remains a part of a bulky, countable, ThO 2 matrix in cladding, protected by the radiation field of all fission products. This highly proliferation-resistant mode of fuel production, as distinct from a reprocessing dominated path via fast breeder reactors (FBR), can bring great acceptability to the enterprise of nuclear fuel production, and insure that scarcity of naturally available U 235 fuel does not throttle expansion of nuclear energy. It also provides a reprocessing free path to energy security for many countries. Ideas and innovations responsible for the creation of a high intensity neutron source are also presented.

Large-scale hydrogen production using nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Ryland, D.; Stolberg, L.; Kettner, A.; Gnanapragasam, N.; Suppiah, S. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

For many years, Atomic Energy of Canada Limited (AECL) has been studying the feasibility of using nuclear reactors, such as the Supercritical Water-cooled Reactor, as an energy source for large scale hydrogen production processes such as High Temperature Steam Electrolysis and the Copper-Chlorine thermochemical cycle. Recent progress includes the augmentation of AECL's experimental capabilities by the construction of experimental systems to test high temperature steam electrolysis button cells at ambient pressure and temperatures up to 850{sup o}C and CuCl/HCl electrolysis cells at pressures up to 7 bar and temperatures up to 100{sup o}C. In parallel, detailed models of solid oxide electrolysis cells and the CuCl/HCl electrolysis cell are being refined and validated using experimental data. Process models are also under development to assess options for economic integration of these hydrogen production processes with nuclear reactors. Options for large-scale energy storage, including hydrogen storage, are also under study. (author)

Particle production from nuclear targets and the structure of hadrons

International Nuclear Information System (INIS)

Bialas, A.

Production processes from nuclear targets allow studying interactions of elementary hadronic constituents in nuclear matter. The information thus obtained on the structure of hadrons and on the properties of hadronic constituents is presented. Both soft (low momentum transfer) and hard (high momentum transfer) processes are discussed. (author)

Production of 15N for nitride type nuclear fuel

International Nuclear Information System (INIS)

Axente, Damian

2005-01-01

Full text: Nitride nuclear fuel is the choice for advanced nuclear reactors and ADS, considering its favorable properties as: melting point, excellent thermal conductivity, high fissile density, lower fission gas release and good radiation tolerance. The application of nitride fuels in different nuclear reactors requires use of 15 N enriched nitrogen to suppress 14 C production due to (n,p) reaction on 14 N. Nitride fuel is a promising candidate for transmutation in ADSs of radioactive minor actinides, which are converted into nitrides with 15 N for that purpose. Taking into account that at present the world wide 15 N market is about 20 - 40 Kg 15 N/y, the supply of that isotope for nitride type nuclear fuel, would demand an increase in production capacity by a factor of 1000. For an industrial plant producing 100 t/y 15 N at 99 at. % 15 N concentration, using present technology of 15 N/ 14 N isotopic exchange in Nitrox system, the first separation stage of the cascade would be fed with 10M HNO 3 solution at a 600 m 3 /h flow-rate. If conversion of HNO 3 into NO, NO 2 , at the enriching end of the columns, would be done with gaseous SO 2 , for an industrial plant of 100 t/y 15 N a consumption of 4 million t SO 2 /y and a production of 70 % H 2 SO 4 waste solution of 4.5 million m 3 /y are estimated. The reconversion of H 2 SO 4 into SO 2 in order to recycle SO 2 is a problem to be solved to compensate the cost of sulfur dioxide and to diminish the amount of sulfuric acid waste solution. It should be taken into consideration an important price reduction of 15 N in order to make possible its utilization for industrial production of nitride type nuclear fuel. (authors)

Technology selection for hydrogen production using nuclear energy

International Nuclear Information System (INIS)

Siti Alimah; Erlan Dewita

2008-01-01

The NPP can either be used to produce electricity, or as heat source for non-electric applications (cogeneration). High Temperature Reactor (HTR) with high outlet coolant temperature around 900~1000 o C, is a reactor type potential for cogeneration purposes such as hydrogen production and other chemical industry processes that need high heat. Considering the national energy policy that a balanced arrangement of renewable and unrenewable natural resources has to be made to keep environmental conservation for the sake of society prosperity in the future, hydrogen gas production using nuclear heat is an appropriate choice. Hydrogen gas is a new energy which is environmentally friendly that it is a prospecting alternative energy source in the future. Within the study, a comparison of three processes of hydrogen gas production covering electrolysis, steam reforming and sulfur-iodine cycle, have been conducted. The parameters that considered are the production cost, capital cost and energy cost, technological status, the independence of fossil fuel, the environmental friendly aspect, as well as the efficiency and the independence of corrosion-resistance material. The study result showed that hydrogen gas production by steam reforming is a better process compared to electrolysis and sulfur-iodine process. Therefore, steam reforming process can be a good choice for hydrogen gas production using nuclear energy in Indonesia. (author)

Detector for gaseous nuclear fission products

International Nuclear Information System (INIS)

Kobayashi, Yoshihiro; Kubo, Katsumi.

1979-01-01

Purpose: To facilitate the fabrication of a precipitator type detector, as well as improve the reliability. Constitution: Gas to be measured flown in an anode is stored in a gas processing system. By applying a voltage between the anode and the cathode, if positively charged Rb or Cs which is the daughter products of gaseous fission products are present in the gas to be measured, the daughter products are successively deposited electrostatically to the cathode. The daughter products issue beta-rays and gamma-rays to ionize the argon gas at the anode, whereby ionizing current flows between both of the electrodes. Pulses are generated from the ionizing current, and presence or absence, as well as the amount of the gaseous fission products are determined by the value recorded for the number of the pulses to thereby detect failures in the nuclear fuel elements. After the completion of the detection, the inside of the anode is evacuated and the cathode is heated to evaporate and discharge the daughter products externally. This eliminates the effects of the former detection to the succeeding detection. (Moriyama, K.)

Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux

Science.gov (United States)

Bowman, Charles D.

1992-01-01

Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux. High thermal neutron fluxes generated from the action of a high power proton accelerator on a spallation target allows the efficient burn-up of higher actinide nuclear waste by a two-step process. Additionally, rapid burn-up of fission product waste for nuclides having small thermal neutron cross sections, and the practicality of small material inventories while achieving significant throughput derive from employment of such high fluxes. Several nuclear technology problems are addressed including 1. nuclear energy production without a waste stream requiring storage on a geological timescale, 2. the burn-up of defense and commercial nuclear waste, and 3. the production of defense nuclear material. The apparatus includes an accelerator, a target for neutron production surrounded by a blanket region for transmutation, a turbine for electric power production, and a chemical processing facility. In all applications, the accelerator power may be generated internally from fission and the waste produced thereby is transmuted internally so that waste management might not be required beyond the human lifespan.

Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux

Science.gov (United States)

Bowman, C.D.

1992-11-03

Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux. High thermal neutron fluxes generated from the action of a high power proton accelerator on a spallation target allows the efficient burn-up of higher actinide nuclear waste by a two-step process. Additionally, rapid burn-up of fission product waste for nuclides having small thermal neutron cross sections, and the practicality of small material inventories while achieving significant throughput derive from employment of such high fluxes. Several nuclear technology problems are addressed including 1. nuclear energy production without a waste stream requiring storage on a geological timescale, 2. the burn-up of defense and commercial nuclear waste, and 3. the production of defense nuclear material. The apparatus includes an accelerator, a target for neutron production surrounded by a blanket region for transmutation, a turbine for electric power production, and a chemical processing facility. In all applications, the accelerator power may be generated internally from fission and the waste produced thereby is transmuted internally so that waste management might not be required beyond the human lifespan.

Managing product complexity: It`s just a matter of time

Energy Technology Data Exchange (ETDEWEB)

Hinckley, C.M.

1998-06-01

It has long been the goal of designers to identify a robust measure of product complexity to guide product decisions. Using Design for Assembly evaluations from over 225 assemblies and subassemblies, alternative measures of product complexity are identified and compared. Time is shown to be the most consistently predicted, useful, and fungible measure. The distribution of assembly times for a product can be modeled by Pareto`s law. This leads to a new, more effective product design guideline and a predictive tool that enables rapid and accurate prediction of assembly times for redesigned products without having to repeat DFMA analysis.

Hydrogen Production from Nuclear Energy via High Temperature Electrolysis

International Nuclear Information System (INIS)

James E. O'Brien; Carl M. Stoots; J. Stephen Herring; Grant L. Hawkes

2006-01-01

This paper presents the technical case for high-temperature nuclear hydrogen production. A general thermodynamic analysis of hydrogen production based on high-temperature thermal water splitting processes is presented. Specific details of hydrogen production based on high-temperature electrolysis are also provided, including results of recent experiments performed at the Idaho National Laboratory. Based on these results, high-temperature electrolysis appears to be a promising technology for efficient large-scale hydrogen production

G.D.F. Suez view on the nuclear energy production

International Nuclear Information System (INIS)

Rorive, P.

2009-01-01

G.D.F. Suez was a pioneer of nuclear energy in Europe. It masters competencies internationally recognized on any part of this sector of energy production ( engineering, services, exploitation, maintenance, nuclear fuels, radioactive waste management, dismantling). it has and exploits 7 units in Belgium, and have capabilities in French nuclear power plants of Chooz and Tricastin. G.D.F. Suez has today ambitious goals in terms of nuclear projects development: to own and operate nuclear power plants of third generation in 2020, to maintain in Europe the share of nuclear in a balanced energy mix and to develop out of Europe a significant capability on several key-markets. To reach these objectives, the group develops an active policy of human resources, research and development and communication in matter of nuclear energy. (N.C.)

Towards nuclear energy applications other than electricity production

International Nuclear Information System (INIS)

Lecomte, M.

2007-01-01

Use of nuclear energy relies on operation of a boiler, involving practically no greenhouse gas emission. Whereas production of electricity is, nowadays, virtually its sole purpose, demand for heat production could equally arise, particularly with the emergence of high-temperature, or even very-high-temperature reactors. With the abilities this involves, as regards the recovery of heavy crude oils from tar sands, seawater desalination, or, most importantly, production of hydrogen by electrolysis, or thermochemistry, this being the energy carrier of tomorrow. (authors)

Separation of the noble metals ruthenium and palladium from nitric acid solution of the nuclear fuel reprocessing containing complexing agents

International Nuclear Information System (INIS)

Ghafourian, H.

1989-06-01

Two extraction chromatographic techniques have been developed. N'N diethylthiourea (DETU), which forms complexes with ruthenium that can be retained on an AG50W-X2 ion exchanger, has proved to be a suitable reagent. The structures of these complexes were elucidated by electrophoresis, ion exchange and IR spectroscopy. Under the same conditions Pd forms an insoluble DETU-complex of the formula [Pd(DETU) 4 ] 2+ , which allows the separation of this metal quantitatively. With regard to the application of the developed technique for recovery of the mentioned noble metals from dissolver residues of the nuclear fuel reprocessing, comparative studies were carried out for accompanying fission product nuclides and actinides such as Mo, Tc, Zr, Ce, U and Pu. It was found out that no complex between diethylthiourea and the fission products zirconium, molybdenum and cerium and the actinides uranium, plutonium and americium were formed. Technetium, which was originally present as pertechnetate, is reduced to Tc(IV) and retained on the cation exchanger together with ruthenium. Ruthenium was eluted with 6 M HNO 3 . The efficiency of the developed process has been demonstrated with simulated solutions. The achieved decontamination factors ranged from 10 2 to 10 6 depending on the nuclide. (orig./RB) [de

Recovery of sodium hydroxide and silica from zirconium oxide plant effluent of Nuclear Fuel Complex

Energy Technology Data Exchange (ETDEWEB)

Bajpai, M B; Shenoi, M R.K.; Keni, V S [Chemical Engineering Division, Bhabha Atomic Research Centre, Mumbai (India)

1994-06-01

Sodium hydroxide (lye) and silica can be recovered in pure form from the alkaline sodium silicate waste of Nuclear Fuel Complex, Hyderabad. Electrolytic method was used to amalgamate the sodium present in an electrolyser with flowing mercury as cathode and nickel as anode. The amalgam is then denuded with water in a graphite packed tower to recover mercury for recycling to the electrolyser and sodium hydroxide lye. Sodium hydroxide lye can be recycled in the zirconium oxide plant. Silica is recovered from the spent electrolyte by ion exchange method using cation exchange resin. Both the process details are described in this paper, with experimental data useful for the scale up. The process converts waste to value products. (author). 3 figs., 2 tabs.

Nuclear photo-meson productions in the 1 GeV energy region

International Nuclear Information System (INIS)

Maeda, Kazushige

1991-01-01

Experimental studies of nuclear photomeson productions in the 1 GeV energy region are discussed. In this energy region, π ± , K + and (η) mesons whose life time (or widths) are enough long (narrow) to use spectroscopic study can be produced. This report focuses a possibility of electro-magnetic K + . productions on nuclei. A preliminary result of a photo-kaon test experiment carried out at electron synchrotron laboratory, Institute for Nuclear Study, University of Tokyo are presented. In this experiment, the particle identification method to select Kaon events has been established. We have performed a first measurement of nuclear photo-kaon cross section. (author)

Nuclear power and health. The implications for health of nuclear power production

International Nuclear Information System (INIS)

1994-01-01

Nuclear power production is, in principle, a safe technology when practised in accordance with the well established and very strict national and international rules and regulations. Yet management failures have occurred, resulting in injuries to personnel and, occasionally, escape of radioactive material. Such events may cause potential health problems, affecting physical, mental and social well-being. Public concern still tends to concentrate on nuclear-power-related facilities, yet the public's desire for a reduction in environmental pollution has led to increased demand for the development and use of low-waste or non-waste energy technologies. Nuclear energy production is one such technology, which has become established and well developed, particularly in highly industrialized countries. This was recognized by the WHO Regional Office for Europe as early as the 1970s, and led to a series of scientific working groups to discuss the most urgent issues related to the impact on health of the generation of electrical power by means of nuclear energy. Five major meetings took place between 1975 and 1985, resulting in five publications (1 - 5) covering various aspects of particular concern to the general public (and thus also to national authorities) such as handling plutonium, managing high-level radioactive waste, and preparing for accidental releases of radioactive material. The first such publication was issued in 1977. All five books were based on the collective knowledge and experience of groups of experts, and were published following the meetings of the respective working groups. The project was initiated at the request and with the support of the Government of Belgium, to study and discuss the effects of the nuclear power industry on people and the environment. The project served two objectives. First, it assisted Member States in developing the capacity to understand the public health implications of the widespread use of nuclear power. Second, it

Calculation of Complexity Costs – An Approach for Rationalizing a Product Program

DEFF Research Database (Denmark)

Hansen, Christian Lindschou; Mortensen, Niels Henrik; Hvam, Lars

2012-01-01

This paper proposes an operational method for rationalizing a product program based on the calculation of complexity costs. The method takes its starting point in the calculation of complexity costs on a product program level. This is done throughout the value chain ranging from component invento...... of a product program. These findings represent an improved decision basis for the planning of reactive and proactive initiatives of rationalizing a product program.......This paper proposes an operational method for rationalizing a product program based on the calculation of complexity costs. The method takes its starting point in the calculation of complexity costs on a product program level. This is done throughout the value chain ranging from component...... inventories at the factory sites, all the way to the distribution of finished goods from distribution centers to the customers. The method proposes a step-wise approach including the analysis, quantification and allocation of product program complexity costs by the means of identifying of a number...

Hazards of nuclear reactors and other major industrial complexes

International Nuclear Information System (INIS)

Farmer, F.R.

1982-01-01

Some of the problems of quantified risk analysis of the hazards of nuclear reactors and other major industrial complexes are raised particularly as seen by the proponents and opponents of atomic energy. These are exemplified by discussing the chemical accidents at Flixborough and Canvey Island and the Light Water Reactor Studies. The role of risk analysis in improving knowledge of the systems studies, improving methods of analysis, identifying weaknesses in systems and in improving engineering/maintenance/operation is also stressed. (U.K.)

Method of manufacturing gadolinium oxide-incorporated nuclear fuel sintering products

International Nuclear Information System (INIS)

Komono, Akira; Seki, Makoto; Omori, Sadayuki.

1987-01-01

Purpose: To manufacture nuclear fuel sintering products excellent in burning property and mechanical property. Constitution: In the manufacturing step for nuclear fuel sintering products, specific metal oxides are added for promoting the growth of crystal grains in the sintering. Those metal oxides melted at a temperature lower than the sintering temperature of a mixture of nuclear fuel oxide powder and oxide power, or those metal oxides causing eutectic reaction are used as the metal oxide. Particularly, those compounds having oxygen atom - metal atom ratio (O/M) of not less than 2 are preferably used. As such metal oxides usable herein transition metal oxides, e.g., Nb 2 O 5 , TiO 2 , MoO 3 and WO 3 are preferred, with Nb 2 O 3 and TiO 2 being preferred particularly. (Seki, T.)

Nuclear Production of Hydrogen Using Thermochemical Water-Splitting Cycles

International Nuclear Information System (INIS)

Brown, L.C.; Besenbruch, G.E.; Schultz, K.R.; Marshall, A.C.; Showalter, S.K.; Pickard, P.S.; Funk, J.F.

2002-01-01

The purpose of this work is to determine the potential for efficient, cost-effective, large-scale production of hydrogen utilizing high-temperature heat from an advanced nuclear power station in a thermochemical water-splitting cycle. We carried out a detailed literature search to create a searchable database with 115 cycles and 822 references. We developed screening criteria to reduce the list to 25 cycles. We used detailed evaluation to select two cycles that appear most promising, the Adiabatic UT-3 cycle and the Sulfur-Iodine cycle. We have selected the Sulfur-Iodine thermochemical water-splitting cycle for further development. We then assessed the suitability of various nuclear reactor types to the production of hydrogen from water using the Sulfur-Iodine cycle. A basic requirement is to deliver heat to the process interface heat exchanger at temperatures up to 900 deg. C. We considered nine categories of reactors: pressurized water-cooled, boiling water-cooled, organic-cooled, alkali metal-cooled, heavy metal-cooled, gas-cooled, molten salt-cooled, liquid-core and gas-core reactors. We developed requirements and criteria to carry out the assessment, considering design, safety, operational, economic and development issues. This assessment process led to our choice of the helium gas-cooled reactor for coupling to the Sulfur-Iodine cycle. In continuing work, we are investigating the improvements that have been proposed to the Sulfur-Iodine cycle and will generate an integrated flowsheet describing a hydrogen production plant powered by a high-temperature helium gas-cooled nuclear reactor. This will allow us to size process equipment and calculate hydrogen production efficiency and capital cost, and to estimate the cost of the hydrogen produced as a function of nuclear reactor cost. (authors)

Cooperation between the Russian Federation and the United States to enhance the existing nuclear-material protection, control, and accounting systems at Mayak Production Association

International Nuclear Information System (INIS)

Starodubtsev, G.S.; Prishchepov, A.I.; Zatorsky, Y.M.; James, L.T.

1997-01-01

The Ministry of the Russian Federation for Atomic Energy (MINATOM) and the US Department of Energy (DOE) are engaged in joint, cooperative efforts to reduce the likelihood of nuclear proliferation by enhancing Material Protection, Control and Accounting (MPC ampersand A) systems in both countries. Mayak Production Association (MPA) is a major Russian nuclear enterprise within the nuclear complex that is operated by MINATOM. This paper describes the nature, scope, and status of the joint, cooperative efforts to enhance existing MPC ampersand A systems at MPA. Current cooperative efforts are focused on enhancements to the existing MPC ampersand A systems at four plants that are operated by MPA and that produce, process, handle and/or store proliferation-sensitive nuclear materials

Cooperation Between the Russian Federation and the United States to Enhance the Existing Nuclear-Material Protection, Control, and Accounting Systems at Mayak Production Association

International Nuclear Information System (INIS)

Cahalane, P.T.; Ehinger, M.H.; James, L.T.; Jarrett, J.H.; Lundgren, R.A.; Manatt, D.R.; Niederauer, G.F.; Olivos, J.D.; Prishchepov, A.I.; Starodubtsev, G.S.; Suda, S.C.; Tittemore, G.W.; Zatorsky, Y.M.

1999-01-01

The Ministry of the Russian Federation for Atomic Energy (MINATOM) and the US Department of Energy (DOE) are engaged in joint, cooperative efforts to reduce the likelihood of nuclear proliferation by enhancing Material Protection, Control and Accounting (MPC and A) systems in both countries. Mayak Production Association (Mayak) is a major Russian nuclear enterprise within the nuclear complex that is operated by lylINATOM. This paper describes the nature, scope, and status of the joint, cooperative efforts to enhance existing MPC and A systems at Mayak. Current cooperative efforts are focused on enhancements to the existing MPC and A systems at two of the plants operated by Mayak that work with proliferation-sensitive nuclear materials

Cooperation between the Russian Federation and the United States to enhance the existing nuclear-material protection, control, and accounting systems at Mayak Production Association

Energy Technology Data Exchange (ETDEWEB)

Starodubtsev, G.S.; Prishchepov, A.I.; Zatorsky, Y.M.; James, L.T. [and others

1997-11-01

The Ministry of the Russian Federation for Atomic Energy (MINATOM) and the US Department of Energy (DOE) are engaged in joint, cooperative efforts to reduce the likelihood of nuclear proliferation by enhancing Material Protection, Control and Accounting (MPC&A) systems in both countries. Mayak Production Association (MPA) is a major Russian nuclear enterprise within the nuclear complex that is operated by MINATOM. This paper describes the nature, scope, and status of the joint, cooperative efforts to enhance existing MPC&A systems at MPA. Current cooperative efforts are focused on enhancements to the existing MPC&A systems at four plants that are operated by MPA and that produce, process, handle and/or store proliferation-sensitive nuclear materials.

Productivity? Domain Complexity vs. Tacit Knowledge

DEFF Research Database (Denmark)

Madsen, Erik Skov; Mikkelsen, Lars Lindegaard

This paper discusses productivity in relation to tacit knowledge (which in the paper is regarded as skills, experiences, competences and attitudes) and domain complexity. The study is based on five very different case studies; three studies are conducted in Den¬mark, China, and the Czech Republic...

Safety culture of complex risky systems: the Nuclear Engineering Institute case study

International Nuclear Information System (INIS)

Obadia, Isaac Jose; Vidal, Mario Cesar Rodriguez; Melo, Paulo Fernando F. Frutuoso e

2002-01-01

Analysis of industrial accidents have demonstrated that safe and reliable operation of complex industrial processes that use risky technology and/or hazard material depends not only on technical factors but on human and organizational factors as well. After the Chernobyl nuclear accident in 1986, the International Atomic Energy Agency established the safety culture concept and started a safety culture enhancement program within nuclear organizations worldwide. The Nuclear Engineering Institute, IEN, is a research and technological development unit of the Brazilian Nuclear Energy Commission, CNEN, characterized as a nuclear and radioactive installation where processes presenting risks to operators and to the environment are executed. In 1999, IEN started a management change program, aiming to achieve excellence of performance, based on the Model of Excellence of the National Quality Award. IEN's safety culture project is based on IAEA methodology and has been incorporated to the organizational management process. This work presents IEN's safety culture project; the results obtained on the initial safety culture assessment and the following project actions. (author)

Product Complexity Impact on Quality and Delivery Performance

DEFF Research Database (Denmark)

Nielsen, Jeppe Bjerrum; Hvam, Lars

2011-01-01

Existing literature on product portfolio complexity is mainly focused on cost related aspects. It is widely acknowledged that an increase in a company’s product portfolio will lead to an increase in complexity related costs such as order management, procurement and inventory. The objective...... is increased, but it is not the only factor affected. We can document that there is a tendency towards increasing lead times as well as a drop in on time delivery and quality for newly introduced product variants. This means that the company experiences a reduced ability to deliver on time while also receiving...... of this article is to examine which other factors that might be affected when a company is expanding its product portfolio, if initiatives are not taken to accommodate this increase. Empirical work carried out in a large international engineering company having a market leader position confirms that cost...

Coevolution between Nuclear-Encoded DNA Replication, Recombination, and Repair Genes and Plastid Genome Complexity.

Science.gov (United States)

Zhang, Jin; Ruhlman, Tracey A; Sabir, Jamal S M; Blazier, John Chris; Weng, Mao-Lun; Park, Seongjun; Jansen, Robert K

2016-02-17

Disruption of DNA replication, recombination, and repair (DNA-RRR) systems has been hypothesized to cause highly elevated nucleotide substitution rates and genome rearrangements in the plastids of angiosperms, but this theory remains untested. To investigate nuclear-plastid genome (plastome) coevolution in Geraniaceae, four different measures of plastome complexity (rearrangements, repeats, nucleotide insertions/deletions, and substitution rates) were evaluated along with substitution rates of 12 nuclear-encoded, plastid-targeted DNA-RRR genes from 27 Geraniales species. Significant correlations were detected for nonsynonymous (dN) but not synonymous (dS) substitution rates for three DNA-RRR genes (uvrB/C, why1, and gyrA) supporting a role for these genes in accelerated plastid genome evolution in Geraniaceae. Furthermore, correlation between dN of uvrB/C and plastome complexity suggests the presence of nucleotide excision repair system in plastids. Significant correlations were also detected between plastome complexity and 13 of the 90 nuclear-encoded organelle-targeted genes investigated. Comparisons revealed significant acceleration of dN in plastid-targeted genes of Geraniales relative to Brassicales suggesting this correlation may be an artifact of elevated rates in this gene set in Geraniaceae. Correlation between dN of plastid-targeted DNA-RRR genes and plastome complexity supports the hypothesis that the aberrant patterns in angiosperm plastome evolution could be caused by dysfunction in DNA-RRR systems. © The Author 2016. Published by Oxford University Press on behalf of the Society for Molecular Biology and Evolution.

Dispersion-strengthened aluminium powder products for nuclear application

DEFF Research Database (Denmark)

Hansen, Niels

1967-01-01

Strength, elongation, corrosion resistance, homogeneity, purity, compatibility with fuel, and resistance to irradiation damage, being main properties of SAP of interest for their application in nuclear technology, are discussed in connection with commercial products; effect on tensile and creep...

Characterization of a novel Dp71 dystrophin-associated protein complex (DAPC) present in the nucleus of HeLa cells: Members of the nuclear DAPC associate with the nuclear matrix

International Nuclear Information System (INIS)

Fuentes-Mera, Lizeth; Rodriguez-Munoz, Rafael; Gonzalez-Ramirez, Ricardo; Garcia-Sierra, Francisco; Gonzalez, Everardo; Mornet, Dominique; Cisneros, Bulmaro

2006-01-01

Dystrophin is an essential component in the assembly and maintenance of the dystrophin-associated protein complex (DAPC), which includes members of the dystroglycan, syntrophin, sarcoglycan and dystrobrevin protein families. Distinctive complexes have been described in the cell membrane of different tissues and cultured cells. In this work, we report the identification and characterization of a novel DAPC present in the nuclei of HeLa cells, which contains dystrophin Dp71 as a key component. Using confocal microscopy and cell fractionation analyses, we found the presence of Dp71, β-sarcoglycan, β-dystroglycan, α- and β-syntrophin, α1- and β-dystrobrevin and nNOS in the nuclei of HeLa cells. Furthermore, we demonstrated by co-immunoprecipitation experiments that most of these proteins form a complex in the nuclear compartment. Next, we analyze the possible association of the nuclear DAPC with the nuclear matrix. We found the presence of Dp71, β-dystroglycan, nNOS, β-sarcoglycan, α/β syntrophin, α1-dystrobrevin and β-dystrobrevin in the nuclear matrix protein fractions and in situ nuclear matrix preparations from HeLa cells. Moreover, we found that Dp71, β-dystroglycan and β-dystrobrevin co-immunoprecipitated with the nuclear matrix proteins lamin B1 and actin. The association of members of the nuclear DAPC with the nuclear matrix indicates that they may work as scaffolding proteins involved in nuclear architecture

Nuclear trafficking of the HIV-1 pre-integration complex depends on the ADAM10 intracellular domain

International Nuclear Information System (INIS)

Endsley, Mark A.; Somasunderam, Anoma D.; Li, Guangyu; Oezguen, Numan; Thiviyanathan, Varatharasa; Murray, James L.; Rubin, Donald H.; Hodge, Thomas W.

2014-01-01

Previously, we showed that ADAM10 is necessary for HIV-1 replication in primary human macrophages and immortalized cell lines. Silencing ADAM10 expression interrupted the HIV-1 life cycle prior to nuclear translocation of viral cDNA. Furthermore, our data indicated that HIV-1 replication depends on the expression of ADAM15 and γ-secretase, which proteolytically processes ADAM10. Silencing ADAM15 or γ-secretase expression inhibits HIV-1 replication between reverse transcription and nuclear entry. Here, we show that ADAM10 expression also supports replication in CD4 + T lymphocytes. The intracellular domain (ICD) of ADAM10 associates with the HIV-1 pre-integration complex (PIC) in the cytoplasm and immunoprecipitates and co-localizes with HIV-1 integrase, a key component of PIC. Taken together, our data support a model whereby ADAM15/γ-secretase processing of ADAM10 releases the ICD, which then incorporates into HIV-1 PIC to facilitate nuclear trafficking. Thus, these studies suggest ADAM10 as a novel therapeutic target for inhibiting HIV-1 prior to nuclear entry. - Highlights: • Nuclear trafficking of the HIV-1 pre-integration complex depends on ADAM10. • ADAM10 associates with HIV-1 integrase in the pre-integration complex. • HIV-1 replication depends on the expression of ADAM15 and γ-secretase. • Silencing ADAM15 or γ-secretase expression inhibits nuclear import of viral cDNA. • ADAM10 is important for HIV-1 replication in human macrophages and CD4 + T lymphocytes

Nuclear trafficking of the HIV-1 pre-integration complex depends on the ADAM10 intracellular domain

Energy Technology Data Exchange (ETDEWEB)

Endsley, Mark A., E-mail: maendsle@utmb.edu [Department Internal Medicine, Division of Infectious Diseases, University of Texas Medical Branch, 301 University Blvd, Galveston, TX 77555 (United States); Somasunderam, Anoma D., E-mail: asomasun@utmb.edu [Department Internal Medicine, Division of Infectious Diseases, University of Texas Medical Branch, 301 University Blvd, Galveston, TX 77555 (United States); Li, Guangyu, E-mail: LIG001@mail.etsu.edu [Department of Internal Medicine, Quillen College of Medicine, East Tennessee State University, Johnson City, TN 37614 (United States); Oezguen, Numan, E-mail: numan.oezguen@bcm.edu [Department of Pathology and Immunology, Microbiome Center, Texas Children' s Hospital, Houston, TX 77030 (United States); Thiviyanathan, Varatharasa, E-mail: Varatharasa.Thiviyanathan@uth.tmc.edu [Institute of Molecular Medicine, University of Texas Health Science Center, Houston, TX 77030 (United States); Murray, James L., E-mail: jmurray100@yahoo.com [GeneTAG Technology, Inc., 3155 Northwoods Place, Norcross, GA 30071 (United States); Rubin, Donald H., E-mail: don.h.rubin@vanderbilt.edu [Research Medicine, VA Tennessee Valley Healthcare System, 1310 24th Ave. South, Nashville, TN 37212 (United States); Departments of Medicine, Pathology, Microbiology and Immunology, Vanderbilt University School of Medicine, 1161 21st Ave South, Nashville, TN 37232 (United States); Hodge, Thomas W., E-mail: twhodge3@gmail.com [Pre-clinical and Antiviral Research, Tamir Biotechnology, Inc., 12625 High Bluff Dr., Suite 113, San Diego, CA 92130 (United States); and others

2014-04-15

Previously, we showed that ADAM10 is necessary for HIV-1 replication in primary human macrophages and immortalized cell lines. Silencing ADAM10 expression interrupted the HIV-1 life cycle prior to nuclear translocation of viral cDNA. Furthermore, our data indicated that HIV-1 replication depends on the expression of ADAM15 and γ-secretase, which proteolytically processes ADAM10. Silencing ADAM15 or γ-secretase expression inhibits HIV-1 replication between reverse transcription and nuclear entry. Here, we show that ADAM10 expression also supports replication in CD4{sup +} T lymphocytes. The intracellular domain (ICD) of ADAM10 associates with the HIV-1 pre-integration complex (PIC) in the cytoplasm and immunoprecipitates and co-localizes with HIV-1 integrase, a key component of PIC. Taken together, our data support a model whereby ADAM15/γ-secretase processing of ADAM10 releases the ICD, which then incorporates into HIV-1 PIC to facilitate nuclear trafficking. Thus, these studies suggest ADAM10 as a novel therapeutic target for inhibiting HIV-1 prior to nuclear entry. - Highlights: • Nuclear trafficking of the HIV-1 pre-integration complex depends on ADAM10. • ADAM10 associates with HIV-1 integrase in the pre-integration complex. • HIV-1 replication depends on the expression of ADAM15 and γ-secretase. • Silencing ADAM15 or γ-secretase expression inhibits nuclear import of viral cDNA. • ADAM10 is important for HIV-1 replication in human macrophages and CD4{sup +} T lymphocytes.

Reconfiguring The Supply Chain For Complex Engineered Products

DEFF Research Database (Denmark)

Wæhrens, Brian Vejrum; Asmussen, Jesper Normann

2016-01-01

of the SC, the product and market requirements. This paper seeks to investigate the factors which create a need for supply chain reconfiguration in the context of the Complex Product Systems, together with the enablers and barriers for successfully realizing supply chain improvements through reconfiguration....

Nuclear pore protein NUP88 activates anaphase-promoting complex to promote aneuploidy

NARCIS (Netherlands)

Naylor, R.M.; Jeganathan, K.B.; Cao, X.; Deursen, J.M. van

2016-01-01

The nuclear pore complex protein NUP88 is frequently elevated in aggressive human cancers and correlates with reduced patient survival; however, it is unclear whether and how NUP88 overexpression drives tumorigenesis. Here, we show that mice overexpressing NUP88 are cancer prone and form intestinal

Processes of hydrogen production, coupled with nuclear reactors: Economic perspectives

International Nuclear Information System (INIS)

Werkoff, Francois; Avril, Sophie; Mansilla, Christine; Sigurvinsson, Jon

2006-01-01

Hydrogen production, using nuclear power is considered from a technic-economic (TE) point of view. Three different processes are examined: Alkaline electrolysis, High-temperature steam electrolysis (HTE) and the thermochemical Sulphur-Iodine (S/I) cycle. The three processes differ, in the sense that the first one is operational and both last ones are still at demonstration stages. For them, it is at present only possible to identify key points and limits of competitiveness. The cost of producing hydrogen by alkaline electrolysis is analysed. Three major contributions to the production costs are examined: the electricity consumption, the operation and maintenance expenditures and the depreciation capital expenditures. A technic-economic evaluation of hydrogen production by HTE coupled to a high-temperature reactor (HTR) is presented. Key points appear to be the electrolyser and the high temperature heat exchangers. The S/I thermochemical cycle is based on the decomposition and the re-composition of H 2 SO 4 and HI acids. The energy consumption and the recovery of iodine are key points of the S/I cycle. With the hypothesis that the hydrogen energy will progressively replace the fossil fuels, we give a first estimate of the numbers of nuclear reactors (EPR or HTR) that would be needed for a massive nuclear hydrogen production. (authors)

Preparation of a primary target for the production of fission products in a nuclear reactor

International Nuclear Information System (INIS)

Arino, H.; Cosolito, F.J.; George, K.D.; Thornton, A.K.

1976-01-01

A primary target for the production of fission products in a nuclear reactor, such as uranium or plutonium fission products, is comprised of an enclosed, cylindrical vessel, preferably comprised of stainless steel, having a thin, continuous, uniform layer of fissionable material, integrally bonded to its inner walls and a port permitting access to the interior of the vessel. A process is also provided for depositing uranium material on to the inner walls of the vessel. Upon irradiation of the target with neutrons from a nuclear reactor, radioactive fission products, such as molybdenum-99, are formed, and thereafter separated from the target by the introduction of an acidic solution through the port to dissolve the irradiated inner layer. The irradiation and dissolution are thus effected in the same vessel without the necessity of transferring the fissionable material and fission products to a separate chemical reactor. Subsequently, the desired isotopes are extracted and purified. Molybdenum-99 decays to technetium-99m which is a valuable medical diagnostic radioisotope. 3 claims, 1 drawing figure

Nuclear data for actinide production and depletion calculations

International Nuclear Information System (INIS)

Benjamin, R.W.

1978-01-01

The status of nuclear cross section data required for actinide depletion calculations in thermal reactors is summarized, and recommendations are made for future work. The primary fertile and fissile nuclides ( 232 Th, 233 U, 235 U, 238 U, and 239 Pu) are not reviewed. Nuclear data for the transactinium mass region are, with few exceptions, reasonably complete and adequate for current thermal-reactor depletion calculations. There is a real need, however, for well-documented reactor production studies to use as benchmarks for data testing. 3 figures, 6 tables

System Theoretic Frameworks for Mitigating Risk Complexity in the Nuclear Fuel Cycle

Energy Technology Data Exchange (ETDEWEB)

Williams, Adam David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Mohagheghi, Amir H. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Cohn, Brian [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Osborn, Douglas M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jones, Katherine A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); DeMenno, Mercy [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kalinina, Elena Arkadievna [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Thomas, Maikael A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Parks, Ethan Rutledge [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Parks, Mancel Jordan [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jeantete, Brian A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-09-01

In response to the expansion of nuclear fuel cycle (NFC) activities -- and the associated suite of risks -- around the world, this project evaluated systems-based solutions for managing such risk complexity in multimodal and multi-jurisdictional international spent nuclear fuel (SNF) transportation. By better understanding systemic risks in SNF transportation, developing SNF transportation risk assessment frameworks, and evaluating these systems-based risk assessment frameworks, this research illustrated interdependency between safety, security, and safeguards risks is inherent in NFC activities and can go unidentified when each "S" is independently evaluated. Two novel system-theoretic analysis techniques -- dynamic probabilistic risk assessment (DPRA) and system-theoretic process analysis (STPA) -- provide integrated "3S" analysis to address these interdependencies and the research results suggest a need -- and provide a way -- to reprioritize United States engagement efforts to reduce global nuclear risks. Lastly, this research identifies areas where Sandia National Laboratories can spearhead technical advances to reduce global nuclear dangers.

DPRK's 4{sup th} Nuclear Test and its Tritium Production

Energy Technology Data Exchange (ETDEWEB)

Kim, Min Soo; Lee, Sang Joon; Chang, Sun Young [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2016-05-15

On January 6, 2016 at 10:30am, the artificial earthquake in the DPRK was detected by multiple international seismic organizations. After 2 hours, the DPRK announced on state TV that 'The first H-bomb test was successfully conducted in the DPRK at 10:00 am on Wednesday, Juche 105(2016), pursuant to the strategic determination of the ruling communist party.' There has been a doubt about the real nature of the DPRK's 4th nuclear test, since 2 months have been passed after its nuclear test. To analyze the nature of the DPRK's nuclear test, it is necessary to check possible options for production of essential materials. The pathways to produce nuclear fusion material (tritium) and to have a relatively high possibility for the DPRK are described in this article. Tritium is key material for H-bomb. And there are two options for the DPRK which are 1) production and 2) illicit trafficking. And this study is focused on production possibility of DPRK. Determination of the nature of DPRK's nuclear test is very hard issue.

Study of the Brazilian scientific production in the nuclear field from 1970 to 1979

International Nuclear Information System (INIS)

Nascimento, M. de J.

1983-01-01

The study of some patterns of the Brazilian scientific literature production - e.g., generated and/or published in Brazil - in the nuclear field included in CIN (Nuclear Information Center) / INIS (International Nuclear Information System) data base from 1970 to 1979 is presented. The purpose is to research: - the growth of the production; - the main subject areas; - the language of the publication; - the literature presentation form; - the author's characterization; - the most productive institutions, their geographical distribution and countries where the literature is published. (E.G.) [pt

Safety issues of nuclear production of hydrogen

International Nuclear Information System (INIS)

Piera, Mireia; Martinez-Val, Jose M.; Jose Montes, Ma

2006-01-01

Hydrogen is not an uncommon issue in Nuclear Safety analysis, particularly in relation to severe accidents. On the other hand, hydrogen is a household name in the chemical industry, particularly in oil refineries, and is also a well known chemical element currently produced by steam reforming of natural gas, and other methods (such as coal gasification). In the not-too-distant future, hydrogen will have to be produced (by chemical reduction of water) using renewable and nuclear energy sources. In particular, nuclear fission seems to offer the cheapest way to provide the primary energy in the medium-term. Safety principles are fundamental guidelines in the design, construction and operation both of hydrogen facilities and nuclear power plants. When these two technologies are integrated, a complete safety analysis must consider not only the safety practices of each industry, but any interaction that could be established between them. In particular, any accident involving a sudden energy release from one of the facilities can affect the other. Release of dangerous substances (chemicals, radiotoxic effluents) can also pose safety problems. Although nuclear-produced hydrogen facilities will need specific approaches and detailed analysis on their safety features, a preliminary approach is presented in this paper. No significant roadblocks are identified that could hamper the deployment of this new industry, but some of the hydrogen production methods will involve very demanding safety standards

Complex products and Systems: Potential from using layout platforms

NARCIS (Netherlands)

Hofer, A.P.; Halman, J.I.M.

2004-01-01

In their quest to manage the complexity of offering greater product variety, firms in many industries are considering platform-based development of product families. Key in this approach is the sharing of components, modules, and other assets across a family of products. Current research indicates

Regulation at nuclear fuel cycle

International Nuclear Information System (INIS)

2002-01-01

This bulletin contains information about activities of the Nuclear Regulatory Authority of the Slovak Republic (UJD). In this leaflet the role of the UJD in regulation at nuclear fuel cycle is presented. The Nuclear Fuel Cycle (NFC) is a complex of activities linked with production of nuclear fuel for nuclear reactors as a source of energy used for production of electricity and heat, and of activities linked with spent nuclear fuel handling. Activities linked with nuclear fuel (NF) production, known as the Front-End of Nuclear Fuel Cycle, include (production of nuclear fuel from uranium as the most frequently used element). After discharging spent nuclear fuel (SNF) from nuclear reactor the activities follow linked with its storage, reprocessing and disposal known as the Back-End of Nuclear Fuel Cycle. Individual activity, which penetrates throughout the NFC, is transport of nuclear materials various forms during NF production and transport of NF and SNF. Nuclear reactors are installed in the Slovak Republic only in commercial nuclear power plants and the NFC is of the open type is imported from abroad and SNF is long-term supposed without reprocessing. The main mission of the area of NFC is supervision over: - assurance of nuclear safety throughout all NFC activities; - observance of provisions of the Treaty on Non-Proliferation of Nuclear Weapons during nuclear material handling; with an aim to prevent leakage of radioactive substances into environment (including deliberated danage of NFC sensitive facilities and misuse of nuclear materials to production of nuclear weapons. The UJD carries out this mission through: - assessment of safety documentation submitted by operators of nuclear installations at which nuclear material, NF and SNF is handled; - inspections concentrated on assurance of compliance of real conditions in NFC, i.e. storage and transport of NF and SNF; storage, transport and disposal of wastes from processing of SNF; with assumptions of the safety

Improvement of computer complex and interface system for compact nuclear simulator

International Nuclear Information System (INIS)

Lee, D. Y.; Park, W. M.; Cha, K. H.; Jung, C. H.; Park, J. C.

1999-01-01

CNS(Compact Nuclear Simulator) was developed at the end of 1980s, and have been used as training simulator for staffs of KAERI during 10 years. The operator panel interface cards and the graphic interface cards were designed with special purpose only for CNS. As these interface cards were worn out for 10 years, it was very difficult to get spare parts and to repair them. And the interface cards were damaged by over current happened by shortage of lamp in the operator panel. To solve these problem, the project 'Improvement of Compact Nuclear Simulator' was started from 1997. This paper only introduces about the improvement of computer complex and interface system

Summary report of the consultants' meeting on nuclear data for production of therapeutic radioisotopes

International Nuclear Information System (INIS)

Haight, R.C.; Paviotti-Corcuera, R.

2002-04-01

This report summarizes the presentations, recommendations and conclusions of the Consultants' Meeting on Nuclear Data for Production of Therapeutic Radioisotopes. The purpose of this meeting was to discuss scientific and technical matters related to the subject and to advise the IAEA Nuclear Data Section (NDS) on the need and possible formation of a Coordinated Research Programme (CRP). Accurate and complete knowledge of nuclear data are essential for the production of radionuclides for therapy to achieve the specific activity and purity required for efficient and safe clinical application. The Consultants recommended updating and completing the data for production of radionuclides that are recognized to be important in therapy. In addition, the consultants recommend investigating other radionuclides that have a potential interest and for which there exists a medical rationale for therapeutic use. To date no serious effort has been devoted to evaluation of nuclear data for the reactor and accelerator production of therapeutic radionuclides. The IAEA is in the unique and privileged position to address this important public health related problem. Therefore, the consultants highly recommend the formation of a CRP with the title: 'Nuclear Data for Production of Therapeutic Radionuclides.' (author)

Utilization of solar and nuclear energy for hydrogen production

International Nuclear Information System (INIS)

Fischer, M.

1987-01-01

Although the world-wide energy supply situation appears to have eased at present, non-fossil primary energy sources and hydrogen as a secondary energy carrier will have to take over a long-term and increasing portion of the energy supply system. The only non-fossil energy sources which are available in relevant quantities, are nuclear energy, solar energy and hydropower. The potential of H 2 for the extensive utilization of solar energy is of particular importance. Status, progress and development potential of the electrolytic H 2 production with photovoltaic generators, solar-thermal power plants and nuclear power plants are studied and discussed. The joint German-Saudi Arabian Research, Development and Demonstration Program HYSOLAR for the solar hydrogen production and utilization is summarized. (orig.)

Economic Analysis for Nuclear Hydrogen Production System Based on HyS Process

International Nuclear Information System (INIS)

Yang, Kyeong Jin; Lee, Ki Young; Lee, Tae Hoon; Chang, Jong Hwa

2009-01-01

The current promising base for massive hydrogen production on high temperature environment derives primarily from three sources: the commercial production of chemicals for the sulfur-iodine (SI) process, the development of solid-oxide fuel cells (SOFC), and the hybrid method of chemicals and fuel cells. The three kinds of process requires high temperature heat energy over 850∼950 .deg. C for the efficient and economic hydrogen production. One of the clean, economic, and moreover promising heat sources supplied to the process is nuclear plants. The nuclear plants producing high temperature heat energy over 950 .deg. C are well known as Very High Temperature Reactors (VHTR) which could have two types of prismatic and pebble-bed cores along reactor core shape. In this paper, we report on the Hybrid Sulfur Process (HyS), and the estimated costs for the system which composes of VHTR of prismatic core type and HyS plant. Nuclear hydrogen production system based on HyS process has been configured to optimally use the thermal energy from VHTR and electric energy to produce hydrogen and oxygen from clean water. High temperature thermal energy is transferred to the HyS process by way of intermediate heat exchanger (IHX) with associated piping. In this paper, the hydrogen production costs for a system composed of a VHTR with six 600MWth module, a power conversion unit (PCU) and a HyS plant are presented, where the thermal energy produced in two module was converted to electric energy in PCU and then transferred to the electrolysis cells for hydrogen production and circulating units on HyS plant, and the remaining thermal energy was supplied to chemical process on HyS plants. As a preliminary study of cost estimates for nuclear hydrogen systems, the hydrogen production costs of the nuclear energy sources benchmarking GT-MHR are estimated in the necessary input data on a Korean specific basis. G4- ECONS was appropriately modified to calculate the cost for hydrogen production

Nuclear power generation and fuel cycle report 1997

International Nuclear Information System (INIS)

1997-09-01

Nuclear power is an important source of electric energy and the amount of nuclear-generated electricity continued to grow as the performance of nuclear power plants improved. In 1996, nuclear power plants supplied 23 percent of the electricity production for countries with nuclear units, and 17 percent of the total electricity generated worldwide. However, the likelihood of nuclear power assuming a much larger role or even retaining its current share of electricity generation production is uncertain. The industry faces a complex set of issues including economic competitiveness, social acceptance, and the handling of nuclear waste, all of which contribute to the uncertain future of nuclear power. Nevertheless, for some countries the installed nuclear generating capacity is projected to continue to grow. Insufficient indigenous energy resources and concerns over energy independence make nuclear electric generation a viable option, especially for the countries of the Far East

Nuclear power generation and fuel cycle report 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-09-01

Nuclear power is an important source of electric energy and the amount of nuclear-generated electricity continued to grow as the performance of nuclear power plants improved. In 1996, nuclear power plants supplied 23 percent of the electricity production for countries with nuclear units, and 17 percent of the total electricity generated worldwide. However, the likelihood of nuclear power assuming a much larger role or even retaining its current share of electricity generation production is uncertain. The industry faces a complex set of issues including economic competitiveness, social acceptance, and the handling of nuclear waste, all of which contribute to the uncertain future of nuclear power. Nevertheless, for some countries the installed nuclear generating capacity is projected to continue to grow. Insufficient indigenous energy resources and concerns over energy independence make nuclear electric generation a viable option, especially for the countries of the Far East.

Rheo-NMR: nuclear magnetic resonance and the rheology of complex fluids

International Nuclear Information System (INIS)

Callaghan, Paul T.

1999-01-01

The application of nuclear magnetic resonance methods to the study of complex fluids under shearing and extensional flows is reviewed. Both NMR velocimetry and spectroscopy approaches are discussed while specific systems studied include polymer melts, rigid rod and random coil polymers in solution, lyotropic and thermotropic liquid crystals and liquid crystalline polymers, and wormlike micelles. Reference is made to food systems. (author)

Influence of the nuclear autocorrelation function on the positron production in heavy-ion collisions

International Nuclear Information System (INIS)

Tomoda, T.; Weidenmueller, H.A.

1983-01-01

The influence of a nuclear reaction on atomic positron production in heavy-ion collisions is investigated. Using statistical concepts, we describe the nuclear S matrix for a heavy-ion induced reaction as a statistically fluctuating function of energy. The positron production rate is then dependent on the autocorrelation function of this S matrix, and on the ratio of the ''direct'' versus the ''fluctuating'' part of the nuclear cross section. Numerical calculations show that in this way, current experimental results on positron production in heavy-ion collisions can be reproduced in a semiquantitative fashion

Discrimination symbol applying method for sintered nuclear fuel product

International Nuclear Information System (INIS)

Ishizaki, Jin

1998-01-01

The present invention provides a symbol applying method for applying discrimination information such as an enrichment degree on the end face of a sintered nuclear product. Namely, discrimination symbols of information of powders are applied by a sintering aid to the end face of a molded member formed by molding nuclear fuel powders under pressure. Then, the molded product is sintered. The sintering aid comprises aluminum oxide, a mixture of aluminum oxide and silicon dioxide, aluminum hydride or aluminum stearate alone or in admixture. As an applying means of the sintering aid, discrimination symbols of information of powders are drawn by an isostearic acid on the end face of the molded product, and the sintering aid is sprayed thereto, or the sintering aid is applied directly, or the sintering aid is suspended in isostearic acid, and the suspension is applied with a brush. As a result, visible discrimination information can be applied to the sintered member easily. (N.H.)

Complex evaluation of ecology situation and soil productivity of Semipalatinsk nuclear test site, perspectives of use

International Nuclear Information System (INIS)

Lebed', L.; Ptiskaya, L.; Lyashenko; Pisak, R.

1996-01-01

Objective of the Project. The goal of the project is complex evaluation of environmental resources at the former Semipalatinsk Test Site and perspectives of their cultivation with taking into account radioactive pollution. Scope of Activities. The following main works at the territory of the former Semipalatinsk Test Site: - estimate of climate, climatic resources and their changes; - organization and realization of complex visual and tool-making air survey (geo botanical, utter satellite spectrometric, radiometric); - reception and computer treatment of space information; - organization and realization of surface expedition field works (radiometric measurements and geo botanical observations); - realization of laboratory analysis for exposure of radio nucleus content in soil, plant and water; - treatment of materials of geo botanical survey, construction of plant and soil maps; - treatment of materials of aero spectrometric and space survey, calculation of vegetation cover productivity, drawing up of computer maps; - assessment of desert and steppe zone vegetation dynamic under artificial and climate impact.Expected Results. The following main investigation results will be obtained first for the territory of Semipalatinsk Test Site and area around it. 1. Objective modern characteristics of radioactive land pollution. Distribution of radio nucleus in soil and vegetation cover. 2. Modern characteristics climatic resources assessment under possible climate change. 3. New maps of vegetation and soil cover, biological and feed productivity of the lands of the polygon at the scale 1:100 000 -1:1 500 000 taking into account climatic resources of the region. 4. Dynamics of desert and steppe zone vegetation assessment under radiation impact and possible climate change. 5. Features of vegetation restoration under constant radiation influence. 6. Basis of perspectives of land cultivation in the Semipalatinsk polygon area and recommendation on rehabilitation soil and

France [National and regional programmes on the production of hydrogen using nuclear energy

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-03-15

Consumption of primary energy in France amounted to 278 Mtoe in 2005, with an average increase of 1.3%/a between 1990 and 2005. The breakdown of primary energy is 42% nuclear energy, 33% oil, 15% natural gas, 6% renewables and 4% coal. France is comparatively poor in domestic energy resources. French coal production, which was still around 40 million t/a at the end of the 1970s, was terminated in 2004. Also, domestic natural gas contributes not more than 2% of France's primary energy production. With the general objectives being to control energy demand, diversify sources of energy, increase research into energy, and provide methods of transporting and storing energy, the French energy policy has given priority to the development of a national energy supply with a strong focus on nuclear energy and renewable energies. These energies are seen to provide a reliable long term supply without GHG emissions and to ensure stable electricity prices. The first nuclear power plants built in France were gas cooled reactors and the country also participated in the OECD Dragon project. Today France is the world's second largest producer of nuclear energy (after the USA) with an electricity share of 78%. France operates 58 nuclear power stations with a total capacity of 63.2 GW. One Gen- III reactor (EPR) is currently under construction. Since nuclear energy is not always fully used, interest is growing in using excess nuclear electricity, apart from export, for hydrogen production to regulate the electricity production.

Analysis of economic and infrastructure issues associated with hydrogen production from nuclear energy

International Nuclear Information System (INIS)

Summers, W.A.; Gorensek, M.B.; Danko, E.; Schultz, K.R.; Richards, M.B.; Brown, L.C.

2004-01-01

Consideration is being given to the large-scale transition of the world's energy system from one based on carbon fuels to one based on the use of hydrogen as the carrier. This transition is necessitated by the declining resource base of conventional oil and gas, air quality concerns, and the threat of global climate change linked to greenhouse gas emissions. Since hydrogen can be produced from water using non-carbon primary energy sources, it is the ideal sustainable fuel. The options for producing the hydrogen include renewables (e.g. solar and wind), fossil fuels with carbon sequestration, and nuclear energy. A comprehensive study has been initiated to define economically feasible concepts and to determine estimates of efficiency and cost for hydrogen production using next generation nuclear reactors. A unique aspect of the study is the assessment of the integration of a nuclear plant, a hydrogen production process and the broader infrastructure requirements. Hydrogen infrastructure issues directly related to nuclear hydrogen production are being addressed, and the projected cost, value and end-use market for hydrogen will be determined. The infrastructure issues are critical, since the combined cost of storing, transporting, distributing, and retailing the hydrogen product could well exceed the cost of hydrogen production measured at the plant gate. The results are expected to be useful in establishing the potential role that nuclear hydrogen can play in the future hydrogen economy. Approximately half of the three-year study has been completed. Results to date indicate that nuclear produced hydrogen can be competitive with hydrogen produced from natural gas for use at oil refineries or ammonia plants, indicating a potential early market opportunity for large-scale centralized hydrogen production. Extension of the hydrogen infrastructure from these large industrial users to distributed hydrogen users such as refueling stations and fuel cell generators could

Characteristic relation for the mass and energy distribution of the nuclear fission products

International Nuclear Information System (INIS)

Alexandru, G.

1977-01-01

The dispersion relation for nuclear fission is written in the two part fragmentation approach which allows to obtain the characteristic relation for the mass and energy distribution of the nuclear fission products. One explains the resonance approximation in the mass distribution of the fission products taking into account the high order resonances too. (author)

Complex monitoring of the surroundings of the Dukovany nuclear power plant

International Nuclear Information System (INIS)

Tylova, E.

1993-01-01

Based on a Resolution of the Government of the Czech Republic, the Ministry of the Environment and the Ministry of Health of the Czech Republic shall develop a project of complex environmental pollution and contamination monitoring in the surroundings of the Dukovany nuclear power plant and shall discuss this project with municipalities there till the end of 1993. The objective of the project is to assess in a complex manner the situation in the Dukovany area with respect to all risks and their simultaneous effects, so as to ensure that the population in the area concerned is not burdened to an intolerable extent. (Z.S.)

Construction labor productivity during nuclear power plant construction

International Nuclear Information System (INIS)

Murray, W.B.

1980-01-01

There is no single satisfactory way to measure productivity in the construction industry. The industry is too varied, too specialized and too dependent upon vast numbers of interrelations between trades, contractors, designers and owners. Hence, no universally reliable indices for measuring construction productivity has been developed. There are problems that are generic to all large union-built nuclear power plants. The actions of any one owner cannot rectify the shortcomings of the construction industry. The generic problems are being identified, and many national organizations are attempting to make the construction industry more productive by recommending various changes

The GIP gamma-tubulin complex-associated proteins are involved in nuclear architecture in Arabidopsis thaliana.

Directory of Open Access Journals (Sweden)

Morgane eBatzenschlager

2013-11-01

Full Text Available During interphase, the microtubular cytoskeleton of cycling plant cells is organized in both cortical and perinuclear arrays. Perinuclear microtubules (MTs are nucleated from γ-Tubulin Complexes (γ-TuCs located at the surface of the nucleus. The molecular mechanisms of γ-TuC association to the nuclear envelope are currently unknown. The γ-TuC Protein 3 (GCP3-Interacting Protein 1 (GIP1 is the smallest γ-TuC component identified so far. AtGIP1 and its homologous protein AtGIP2 participate in the localization of active γ-TuCs at interphasic and mitotic MT nucleation sites. Arabidopsis gip1gip2 mutants are impaired in establishing a fully functional mitotic spindle and exhibit severe developmental defects.In this study, gip1gip2 knock down mutants were further characterized at the cellular level. In addition to defects in both the localization of γ-TuC core proteins and MT fibre robustness, gip1gip2 mutants exhibited a severe alteration of the nuclear shape associated with an abnormal distribution of the nuclear pore complexes. Simultaneously, they showed a misorganization of the inner nuclear membrane protein AtSUN1. Furthermore, AtGIP1 was identified as an interacting partner of AtTSA1 which was detected, like the AtGIP proteins, at the nuclear envelope.These results provide the first evidence for the involvement of a γ-TuC component in both nuclear shaping and nuclear envelope organization. Functional hypotheses are discussed in order to propose a model for a GIP-dependent nucleo-cytoplasmic continuum.

The basic route of the nuclear translocation porcine growth hormone (GH)-growth hormone receptor (GHR) complex (pGH/GHR) in porcine hepatocytes.

Science.gov (United States)

Hainan, Lan; Huilin, Liu; Khan, Mahamad; Xin, Zheng; YuJiang, Yang; Hui, Zhang; Naiquan, Yao

2018-06-08

Traditional views suggest that growth hormone and the growth hormone receptor (GH/GHR complex) exert their functions only on the plasma membrane. This paradigm, however, has been challenged by recent new findings that the GH/GHR complex could translocate into cell nuclei where they could still exhibit important physiological functions. We also reported the nuclear localization of porcine GH/GHR and their potential functions in porcine hepatocytes. However, the basic path of pGH/GHR's nuclear translocation remains unclear. Combining previous research results and our current findings, we proposed two basic routes of pGH/GHR's nuclear transportation as follows: 1) after pGH binding to GHR, pGH/GHR enters into the cytoplasm though clathrin- or caveolin-mediated endocytosis, then the pGH/GHR complex enters into early endosomes (Rab5-positive), and the endosome carries the GH/GHR complex to the endoplasmic reticulum (ER). After endosome docking on the ER, the endosome starts fission, and the pGH/GHR complex enters into the ER lumen. Then the pGH/GHR complex transports into the cytoplasm, possibly by the ERAD pathway. Subsequently, the pGH/GHR complex interacts with IMPα/β, which, in turn, mediates GH/GHR nuclear localization; 2) pGH binds with the GHR on the cell membrane and, subsequently, pGH/GHR internalizes into the cell and enters into the endosome (this endosome may belong to a class of endosomes called envelope-associated endosomes (NAE)). Then, the endosome carries the pGH/GHR to the nuclear membrane. After docking on the nuclear membrane, the pGH/GHR complex fuses with the nuclear membrane and then enters into the cell nucleus. Copyright © 2018 Elsevier Inc. All rights reserved.

Assembly factors for the membrane arm of human complex I.

Science.gov (United States)

Andrews, Byron; Carroll, Joe; Ding, Shujing; Fearnley, Ian M; Walker, John E

2013-11-19

Mitochondrial respiratory complex I is a product of both the nuclear and mitochondrial genomes. The integration of seven subunits encoded in mitochondrial DNA into the inner membrane, their association with 14 nuclear-encoded membrane subunits, the construction of the extrinsic arm from 23 additional nuclear-encoded proteins, iron-sulfur clusters, and flavin mononucleotide cofactor require the participation of assembly factors. Some are intrinsic to the complex, whereas others participate transiently. The suppression of the expression of the NDUFA11 subunit of complex I disrupted the assembly of the complex, and subcomplexes with masses of 550 and 815 kDa accumulated. Eight of the known extrinsic assembly factors plus a hydrophobic protein, C3orf1, were associated with the subcomplexes. The characteristics of C3orf1, of another assembly factor, TMEM126B, and of NDUFA11 suggest that they all participate in constructing the membrane arm of complex I.

The prevalence at birth of congenital malformations in the city of Ozyorsk located near the nuclear complex Mayak production association

Energy Technology Data Exchange (ETDEWEB)

Petrushkina, N. P.; Koshurnikova, N. A.; Okatenko, P. V.

2004-07-01

For many years possible genetic effects of exposure to ionizing radiation have been a subject of interest and concern, but data from studies of the risk of radiation-induced hereditary effects in humans are limited. the most extensive human studies of genetic effects were those conducted on the Japanese. A-bomb survivors. In These studies in investigators examined the association of various levels of radiation exposure and several different endpoints, including major congenital defects, stillbirth, death during the first week of life, survivals, and sex ratio and Down's syndrome (8, (14-16). Although associations of these outcomes with radiation exposure were in the positive direction, none were close to statistical significance. Only teratogenic effects of in utero exposure at Hiroshima and Nagasaki, microcephaly and mental retardation, have been observed (8, (10, 16)). Of most interest is possible association of congenital malformations (CMs) with parental occupational radiation exposure. Determination of the role of parental occupational exposure in induction of CMs in children is necessary to evaluate reliability of radiation protection standards Epidemiological studies conducted on the basis of Registries of children who were born in regions located near a nuclear complex may be useful for such evaluation. It is preferable to carry out such studies on the basis of population registries, since long follow-up in large populations allows to reveal increased frequency of even very rare forms of congenital abnormalities. In a case-control study of association of parental occupational exposure due to Hanford Nuclear Site and risk of CMs in their offspring there was no evidence of such an association (12, 13). Our investigation is conducted on the basis of the basis of the Registry of children of Ozyorsk. The whole Registry includes all children with 1948-1988 birth years show were born or-came to town at the age of 0-14 years, and were residents of these towns

The prevalence at birth of congenital malformations in the city of Ozyorsk located near the nuclear complex Mayak production association

International Nuclear Information System (INIS)

Petrushkina, N. P.; Koshurnikova, N. A.; Okatenko, P. V.

2004-01-01

For many years possible genetic effects of exposure to ionizing radiation have been a subject of interest and concern, but data from studies of the risk of radiation-induced hereditary effects in humans are limited. the most extensive human studies of genetic effects were those conducted on the Japanese. A-bomb survivors. In These studies in investigators examined the association of various levels of radiation exposure and several different endpoints, including major congenital defects, stillbirth, death during the first week of life, survivals, and sex ratio and Down's syndrome (8, (14-16). Although associations of these outcomes with radiation exposure were in the positive direction, none were close to statistical significance. Only teratogenic effects of in utero exposure at Hiroshima and Nagasaki, microcephaly and mental retardation, have been observed (8, (10, 16)). Of most interest is possible association of congenital malformations (CMs) with parental occupational radiation exposure. Determination of the role of parental occupational exposure in induction of CMs in children is necessary to evaluate reliability of radiation protection standards Epidemiological studies conducted on the basis of Registries of children who were born in regions located near a nuclear complex may be useful for such evaluation. It is preferable to carry out such studies on the basis of population registries, since long follow-up in large populations allows to reveal increased frequency of even very rare forms of congenital abnormalities. In a case-control study of association of parental occupational exposure due to Hanford Nuclear Site and risk of CMs in their offspring there was no evidence of such an association (12, 13). Our investigation is conducted on the basis of the basis of the Registry of children of Ozyorsk. The whole Registry includes all children with 1948-1988 birth years show were born or-came to town at the age of 0-14 years, and were residents of these towns one

Multiparticle production in particle and nuclear collisions, 2

International Nuclear Information System (INIS)

Kanki, Takeshi; Kinoshita, Kisei; Sumiyoshi, Hiroyuki; Takagi, Fujio.

1990-01-01

Multiparticle dynamics is related to many branches of particle and nuclear physics. This book provides a comprehensive review which covers the whole domain of multiparticle dynamics. The review consists of five chapters. Chapter D, which is the first chapter of this volume, is titled 'Mechanism of Fragmentation' and contains six sections dealing with 'parton densities inside hadrons', 'hadron fragmentation and quark picture', 'recombination type models', 'quark fragmentation models in soft interaction', 'diquark and its fragmentation' and 'fragmentation in string models'. Chapter E 'Diffractive Production of Hadrons' discusses 'diffractive inelastic processes of composite particles', 'diffractive processes and triple-pomeron coupling', 'properties of diffractive inelastic final states', and 'nature of pomeron'. Chapter F 'Unified Descriptions' focuses on 'general chain picture', 'dual parton model', 'Monte Carlo simulations' and 'unification of hard and soft interactions'. Chapter G, titled 'Multiparticle Production in Hadron-Nucleus Collisions and Other Nuclear Processes' and contains 11 sections. Chapter H presents conclusions. (N.K.)

The virtual product-process design laboratory to manage the complexity in the verification of formulated products

DEFF Research Database (Denmark)

Conte, Elisa; Gani, Rafiqul; Malik, Tahir I.

2011-01-01

-Process Design laboratory (virtual PPD-lab) software is based on this decomposition strategy for the design of formulated liquid products. When the needed models are available in the software, the solution of formulation design/verification problems is straightforward, while when models are not available...... mixtures need to be predicted. This complexity has to be managed through decomposition of the problem into sub-problems. Each sub-problem is solved and analyzed and, from the knowledge gained, an overall evaluation of the complex chemical system representing the product is made. The virtual Product...... in the software library, they need to be developed and/or implemented. The potential of the virtual PPD-lab in managing the complexity in the verification of formulated products, after the needed models have been developed and implemented, is highlighted in this paper through a case study from industry dealing...

Smoke production from multiple nuclear explosions in nonurban areas

International Nuclear Information System (INIS)

Small, R.D.; Bush, B.W.

1985-01-01

The amount of smoke that may be produced by wildland or rural fires as a consequence of a large-scale nuclear exchange is estimated. The calculation is based on a compilation of rural military facilities, identified from a wide variety of unclassified sources, together with data on their geographic positions, surrounding vegetation (fuel), and weather conditions. The ignition area (corrected for fuel moisture) and the amount of fire spread are used to calculate the smoke production. The results show a substantially lower estimated smoke production (from wildland fires) than in earlier nuclear winter studies. The amount varies seasonally and at its peak is less by an order of magnitude than the estimated threshold level necessary for a major attenuation of solar radiation. 32 references, 6 figures, 2 tables

SYSTEM ANALYSIS OF NUCLEAR-ASSISTED SYNGAS PRODUCTION FROM COAL

International Nuclear Information System (INIS)

E. A. Harvego; M. G. McKellar; J. E. O'Brien

2008-01-01

A system analysis has been performed to assess the efficiency and carbon utilization of a nuclear-assisted coal gasification process. The nuclear reactor is a high-temperature helium-cooled reactor that is used primarily to provide power for hydrogen production via high-temperature electrolysis. The supplemental hydrogen is mixed with the outlet stream from an oxygen-blown coal gasifier to produce a hydrogen-rich gas mixture, allowing most of the carbon dioxide to be converted into carbon monoxide, with enough excess hydrogen to produce a syngas product stream with a hydrogen/carbon monoxide molar ratio of about 2:1. Oxygen for the gasifier is also provided by the high-temperature electrolysis process. Results of the analysis predict 90.5% carbon utilization with a syngas production efficiency (defined as the ratio of the heating value of the produced syngas to the sum of the heating value of the coal plus the high-temperature reactor heat input) of 66.1% at a gasifier temperature of 1866 K for the high-moisture-content lignite coal considered. Usage of lower moisture coals such as bituminous can yield carbon utilization approaching 100% and 70% syngas production efficiency

System Analysis of Nuclear-Assisted Syngas Production from Coal

International Nuclear Information System (INIS)

Harvego, E.A.; McKellar, M.G.; O'Brien, J.E.

2009-01-01

A system analysis has been performed to assess the efficiency and carbon utilization of a nuclear-assisted coal gasification process. The nuclear reactor is a high-temperature helium-cooled reactor that is used primarily to provide power for hydrogen production via high temperature electrolysis. The supplemental hydrogen is mixed with the outlet stream from an oxygen-blown coal gasifier to produce a hydrogen-rich gas mixture, allowing most of the carbon dioxide to be converted into carbon monoxide, with enough excess hydrogen to produce a syngas product stream with a hydrogen/carbon monoxide molar ratio of about 2:1. Oxygen for the gasifier is also provided by the high-temperature electrolysis process. Results of the analysis predict 90.5% carbon utilization with a syngas production efficiency (defined as the ratio of the heating value of the produced syngas to the sum of the heating value of the coal plus the high-temperature reactor heat input) of 64.4% at a gasifier temperature of 1866 K for the high-moisture-content lignite coal considered. Usage of lower moisture coals such as bituminous can yield carbon utilization approaching 100% and 70% syngas production efficiency.

Analysis of Product Complexity considering Disruption Cost in Fast Fashion Supply Chain

Directory of Open Access Journals (Sweden)

Shaheen Sardar

2015-01-01

Full Text Available Outsourcing in the textile industry has been playing an important role in the global economy for six decades. Recently, reshoring is an emerging trend due to various complexities involved in supply chain management. As compared with basic textile and apparel products, fast fashion products are complex in their own way. A single assortment contains several new styles, colors, and sizes with unpredictable demand and urgent deadlines. Numerous assortments run simultaneously in the supply chain. For each assortment, the garment manufacturer has to source various types of fabrics and materials from different suppliers and then manufacture the garments to ship within the deadlines. This complexity contributes to supply chain disruption. This paper develops a model to estimate supply chain disruption cost as a function of fast fashion product complexity in the global outsourcing environment. Estimation of disruption cost will help us to increase visibility and eliminate the bottlenecks in supply chain. Model conclusions are used to develop a method to manage the level of product complexity from the global supply chain perspective. Several strategies are proposed to manage the impact of product complexity on supply chain design.

Dynamic Simulation and Optimization of Nuclear Hydrogen Production Systems

Energy Technology Data Exchange (ETDEWEB)

Paul I. Barton; Mujid S. Kaximi; Georgios Bollas; Patricio Ramirez Munoz

2009-07-31

This project is part of a research effort to design a hydrogen plant and its interface with a nuclear reactor. This project developed a dynamic modeling, simulation and optimization environment for nuclear hydrogen production systems. A hybrid discrete/continuous model captures both the continuous dynamics of the nuclear plant, the hydrogen plant, and their interface, along with discrete events such as major upsets. This hybrid model makes us of accurate thermodynamic sub-models for the description of phase and reaction equilibria in the thermochemical reactor. Use of the detailed thermodynamic models will allow researchers to examine the process in detail and have confidence in the accurary of the property package they use.

What is the subject of decision-making in the management of development and operation of a nuclear power complex

International Nuclear Information System (INIS)

Drahny, M.

1986-01-01

Decision-making in the nuclear power complex is described in context with the respective process of management. Basic concepts are defined, the course of an elementary decision-making process described and basic knowledge is generalized for more complex actual cases. Conditions are studied which determine the quality of adopted decisions. Special attention is devoted to working papers for the decision-making process and to the compilers of such papers. Items of decision-making in the nuclear power complex are classified in time sequence and system hierarchy. (author)

The Arabidopsis Nuclear Pore and Nuclear Envelope

OpenAIRE

Meier, Iris; Brkljacic, Jelena

2010-01-01

The nuclear envelope is a double membrane structure that separates the eukaryotic cytoplasm from the nucleoplasm. The nuclear pores embedded in the nuclear envelope are the sole gateways for macromolecular trafficking in and out of the nucleus. The nuclear pore complexes assembled at the nuclear pores are large protein conglomerates composed of multiple units of about 30 different nucleoporins. Proteins and RNAs traffic through the nuclear pore complexes, enabled by the interacting activities...

Natural gas production from underground nuclear explosions

Energy Technology Data Exchange (ETDEWEB)

1965-01-01

A remote location in Rio Arriba County, NW. New Mexico, is being considered as the site for an experiment in the use of a nuclear explosive to increase production from a natural gas field. A feasibility study has been conducted by the El Paso Natural Gas Co., the U.S. Atomic Energy commission, and the U.S. Bureau of Mines. As presently conceived, a nuclear explosive would be set in an emplacement hole and detonated. The explosion would create a cylinder or ''chimney'' of collapsed rock, and a network of fractures extending beyond the chimney. The fractures are the key effect. These would consist of new fractures, enlargement of existing ones, and movement along planes where strata overlap. In addition, there are a number of intangible but important benefits that could accrue from the stimulating effect. Among these are the great increase in recoverable reserves and the deliverability of large volumes of gas during the periods of high demand. It is believed that this type of well stimulation may increase the total gas production of these low permeability natural gas fields by about 7 times the amounts now attainable.

Operational experience with propulsion nuclear plants

International Nuclear Information System (INIS)

Polunichev, V.

2000-01-01

Russia possesses a powerful icebreaker transport fleet which offers a solution for important socio-economic tasks of the country's northern regions by maintaining a year-round navigation along the Arctic Sea route. The total operating record of the propulsion nuclear reactors till now exceeds 150 reactor-years, their main equipment items operating life amounted to 120,000 h. Progressive design-constructional solutions being perfected continuously during 40 years of nuclear-powered ships creation in Russia and well proven technology of all components used in the marine nuclear reactors give grounds to recommend marine Nuclear Steam Supply Systems (NSSSs) of KLT-40 type as energy sources for heat and power cogeneration plants and sea water desalination complexes, particularly as floating installations. Co-generation stations are considered for deployment in the extreme north of Russia. Nuclear floating desalination complexes can be used for drinkable water production in coastal regions of Northern Africa, the Near East, India etc. (author)

Construction labor productivity during nuclear power plant construction

International Nuclear Information System (INIS)

Murray, W.B.

1980-01-01

This paper discusses the three different types of productivity programs used at the Wm. H. Zimmer Nuclear Power Station construction site. The Standard Cost Estimate as Productivity Measurement compares actual units installed to estimated units. The Manpower and Equipment Utilization Study measures the present utilization level of the construction work force, identifies opportunities for productivity improvement, and establishes a data base against which future improvements could be made. The special productivity program is a specialized and detailed study of first line supervision. Productivity is defined as the degree of efficiency attained in the use of labor, professional and management skills and knowledge, materials and equipment, and time and money to produce an end result. It is concluded that a more consistent system of productivity measurements needs to be developed and promoted for general use in the construction industry

Comparative anatomy of the vestibular nuclear complex in submammalian vertebrates.

Science.gov (United States)

Mehler, W. R.

1972-01-01

A synopsis of the literature on the natural history of the vestibular nuclear complex (VNC) in lower vertebrates is presented in an attempt to assess the knowledge available. The review discloses that there is considerable descriptive information that is widely dispersed in the literature. However, information about the topology, number, and cellular composition of the cell groups that compose the VNC is sketchy. Major cytological and hodological information is still needed to establish which parts of the VNC actually are homologous.

Continuous radiochemical analysis of fission products in a nuclear reactor water coolant

International Nuclear Information System (INIS)

Moskvin, L.N.; Zakharov, L.K.; Leont'ev, G.G.; Mel'nikov, V.A.; Orlenkov, I.S.; Slutskij, G.K.

1975-01-01

Method for continuous radiochemical analysis of I, Cs, Ba, Sr and Ce isotopes in a reactor water heat-transfer agent was developed. A continuous two-dimensional chromatographic process of complex mixtures separation of substances proved to be feasible on several parallel sorbent layers, which moved at constant velocities and separated by stationary intermediate collectors. Tests on model solutions containing I, Ce, Cs and Ba isotopes and on heat-carrier samples showed quantitative separation of elements. The results were indicative of a basic possibility of using multisorbent chromatographs for continuous control of multicomponent mixtures, particularly for control of radioactive fission product compositions in water heat-transfer agents in nuclear power plants. A diagram is shown for a two-dimensional chromatographic separation of a multicomponent mixture. Also shown is a flow chart of an installation for continuous control of iodine and cesium isotope activities

Fundamentals of nuclear chemistry

International Nuclear Information System (INIS)

Majer, V.

1982-01-01

The author of the book has had 25 years of experience at the Nuclear Chemistry of Prague Technical University. In consequence, the book is intended as a basic textbook for students of this field. Its main objectives are an easily understandable presentation of the complex subject and in spite of the uncertainty which still characterizes the definition and subjects of nuclear chemistry - a systematic classification and logical structure. Contents: 1. Introduction (history and definition); 2. General nuclear chemistry (physical fundamentals, hot atom chemistry, interaction of nuclear radiation with matter, radioactive elements, isotope effects, isotope exchange, chemistry of radioactive trace elements); 3. Methods of nuclear chemistry of nuclear chemistry (radiochemical methods, activation, separation and enrichment chemistry); 4. Preparative nuclear chemistry (isotope production, labelled compounds); 5. Analytival nuclear chemistry; 6. Applied nuclear chemistry (isotope applications in general physical and analytical chemistry). The book is supplemented by an annex with tables, a name catalogue and a subject index which will facilitate access to important information. (RB) [de

San Rafael mining and fabrication complex today

International Nuclear Information System (INIS)

Navarra, Pablo; Aldebert, Sergio R.

2005-01-01

In Mendoza province, 35 km West San Rafael city, is located a CNEA installation for uranium ore extraction and concentration: the San Rafael Mining and Fabrication Complex. By the middle of the nineties, as a consequence of the very low prices of uranium concentrate in the international market and of the high internal production costs, uranium extraction was stopped. To day, the international price of the concentrate had a very important increase and the Government has decided the completion of the Atucha II Nuclear Power Station construction. Moreover, studies have been started for new nuclear power plants. In such circumstances the reactivation of the Complex will make sure the uranium supply for our nuclear power stations, contributing to the improvement of the energy generation mix in our country. (author) [es

Water-Soluble Coenzyme Q10 Inhibits Nuclear Translocation of Apoptosis Inducing Factor and Cell Death Caused by Mitochondrial Complex I Inhibition

Directory of Open Access Journals (Sweden)

Haining Li

2014-07-01

Full Text Available The objectives of the study were to explore the mechanism of rotenone-induced cell damage and to examine the protective effects of water-soluble Coenzyme Q10 (CoQ10 on the toxic effects of rotenone. Murine hippocampal HT22 cells were cultured with mitochondrial complex I inhibitor rotenone. Water-soluble CoQ10 was added to the culture media 3 h prior to the rotenone incubation. Cell viability was determined by alamar blue, reactive oxygen species (ROS production by dihydroethidine (DHE and mitochondrial membrane potential by tetramethyl rhodamine methyl ester (TMRM. Cytochrome c, caspase-9 and apoptosis-inducing factor (AIF were measured using Western blotting after 24 h rotenone incubation. Rotenone caused more than 50% of cell death, increased ROS production, AIF nuclear translocation and reduction in mitochondrial membrane potential, but failed to cause mitochondrial cytochrome c release and caspase-9 activation. Pretreatment with water-soluble CoQ10 enhanced cell viability, decreased ROS production, maintained mitochondrial membrane potential and prevented AIF nuclear translocation. The results suggest that rotenone activates a mitochondria-initiated, caspase-independent cell death pathway. Water-soluble CoQ10 reduces ROS accumulation, prevents the fall of mitochondrial membrane potential, and inhibits AIF translocation and subsequent cell death.

Is there an antagonism between nuclear safety and productivity?

International Nuclear Information System (INIS)

Dessus de Cerou, E.; Fourest, B.; Frantzen, C.; Lacoste, A.C.

1999-01-01

This article reviews the conference organized by the SFEN on November 10, 1998. The object of this meeting was to overview the recent dispositions taken by EdF about the management of its nuclear power plants. The creation of OSD (safety-availability-observatories) in each nuclear plant, whose purpose is to set a dialogue between the demands of safety and the optimization of production shows the importance given by EdF to provide a safe and competitive energy. It shows also the will of EdF to acknowledge the existence of real conflicts between radiation protection, quality assurance and competitiveness in the daily life of a nuclear facility. EdF will face a partial opening of its market by february 2000 within the limits defined by European regulations. This increase of competition could rise problems between the transparency of nuclear activities, patent rights and information reporting. (A.C.)

Natural radiation - a perspective to radiological risk factors of nuclear energy production

DEFF Research Database (Denmark)

Mustonen, R.; Christensen, T.; Stranden, E.

1992-01-01

Radiation doses from natural radiation and from man-made modifications on natural radiation, and different natural radiological environments in the Nordic countries are summarized and used as a perspective for the radiological consequences of nuclear energy production. The significance of different...... radiation sources can be judged against the total collective effective dose equivalent from natural radiation in the Nordic countries, 92 000 manSv per year. The collective dose from nuclear energy production during normal operation is estimated to 20 manSv per year and from non-nuclear energy production...... to 80 manSv per year. The increase in collective dose due to the conservation of heating energy in Nordic dwellings is estimated to 23 000 manSv per year, from 1973 to 1984. An indirect radiological danger index is defined in order to be able to compare the significance of estimated future releases...

Uptake of actinides and nuclear fission products in graminaceous and nongraminaceous plants

Science.gov (United States)

Ely, Stephanie Lynn

Radionuclides exist within the environment naturally and also from release during nuclear power and weapons production. The ability of plants to uptake radionuclides may prove beneficial for exploitation in the field of phytoremediation and as a biomonitor within the field of nuclear forensics. The fact that plants have the ability to take up radionuclides as an unintended metabolic process is well known, however, the mechanisms through which uptake occur present large gaps within the current research. Therefore, gaining further knowledge regarding overall plant radionuclide uptake and specific mechanisms may prove as an invaluable tool to enhance phytoremediation and nuclear forensic efforts. Within this work, controlled laboratory experiments were conducted in order to determine any uptake differences between graminaceous (rye grass) and nongraminaceous (cucumber) plants. A matrix of samples were individually spiked with known amounts of Sr, Cs, Th, U as well as ligands of acetate, citrate, DFOB. Uptake was compared through the calculation and analysis of distribution coefficients within the roots and shoots of each plant sample. A variety of trends were observed throughout this study. Overall, it was determined that the cucumber plant takes up slightly higher concentrations within both the roots and the shoots, except for within the Cs set of samples. Within the Cs samples it was determined that uptake was much higher in the rye grass than in the cucumber plant. Therefore, it was concluded that it may be more beneficial to focus on the collection of grasses and other graminaceous plants when the goal is to collect a plant to determine nuclear activity within the vicinity of a facility. This is due to the fact that Cs is generally released at higher concentrations than other radionuclides during the process of nuclear power and energy production. Similarly, grasses may also be desired as the main focus for phytoremediation efforts due to the fact that Cs is a

Qualitative and quantitative characteristics of fission products in spent nuclear fuel from RBMK-type reactor

International Nuclear Information System (INIS)

Adlys, G.; Adliene, D.

2002-01-01

Well-known empirical models or experimental instruments and methods for the estimation of fission product yields do not allow prediction of the behavior and evaluation of the time-dependent qualitative and quantitative characteristics of all fission products in spent nuclear fuel during long-term storage. Several computer codes were developed in different countries to solve this problem. French codes APOLLO1 and PEPIN were used in this work for modeling the characteristics of spent nuclear fuel in the RBMK reactor. The modeling results of qualitative and quantitative characteristics of long-lived fission products for different cooling periods of spent nuclear fuel, including 50-year cooling period, are presented in this paper. The 50-year cooling period conforms to the foreseen time of storage of spent nuclear fuel in CONSTOR and CASTOR casks at the Ignalina NPP. These results correlate well with evaluated quantities for the well-known yields of the nuclides and could be used for the compilation of the database for long-lived fission products in spent nuclear fuel from the RBMK-type reactor. They allow one to predict and to solve effectively safety problems concerning with long-term spent nuclear fuel storage in casks. (author)

Production of Radioisotopes and Radiopharmaceuticals at the Dalat Nuclear Research Reactor

International Nuclear Information System (INIS)

Duong Van Dong; Pham Ngoc Dien; Bui Van Cuong; Mai Phuoc Tho; Nguyen Thi Thu; Vo Thi Cam Hoa

2014-01-01

After reconstruction, the Dalat Nuclear Research Reactor (DNRR) was inaugurated on March 20th, 1984 with the nominal power of 500 kW. Since then the production of radioisotopes and labelled compounds for medical use was started. Up to now, DNRR is still the unique one in Vietnam. The reactor has been operated safely and effectively with the total of about 37,800 hrs (approximately 1,300 hours per year). More than 90% of its operation time and over 80% of its irradiation capacity have been exploited for research and production of radioisotopes. This paper gives an outline of the radioisotope production programme using the DNRR. The production laboratory and facilities including the nuclear reactor with its irradiation positions and characteristics, hot cells, production lines and equipment for the production of Kits for labelling with 99m Tc and for quality control, as well as the production rate are mentioned. The methods used for production of 131 I, 99m Tc, 51 Cr, 32 P, etc. and the procedures for preparation of radiopharmaceuticals are described briefly. Status of utilization of domestic radioisotopes and radiopharmaceuticals in Vietnam is also reported. (author)

Platform strategy for complex products and systems

NARCIS (Netherlands)

Alblas, A.A.

2011-01-01

The thesis of Alex Alblas presents a design reuse strategy for firms producing complex products and systems (CoPS). Examples of CoPS include industrial machinery, oil-rigs, electrical power distribution systems, integrated mail processing systems and printing press machinery. CoPS firms are

Depleted uranium as a by product of nuclear technology

International Nuclear Information System (INIS)

Orlic, M.

2000-01-01

Depleted uranium (DU) has been used during the War in Yugoslavia in the year 1999 by NATO forces, as well as in Bosnia and Gulf War. In Yugoslavia it has been used in two modalities: as ammunition (mostly caliber 30 mm) and as a part of cruise missiles (counterweight penetrator). Total amount of DU in Yugoslavia was about 10 tons. DU is a by product of nuclear technology and represents low-level nuclear waste. Therefore it should be stored. But, because of military application it is in the environment where it could react chemo toxically or radio toxically and so endanger people and animals. This paper contains all relevant technology parameters of DU created as a by product, DU physical and chemical properties, DU ammunition effects, environmental DU transport, and estimation of consequences on people and environment

LARGE-SCALE PRODUCTION OF HYDROGEN BY NUCLEAR ENERGY FOR THE HYDROGEN ECONOMY

International Nuclear Information System (INIS)

SCHULTZ, K.R.; BROWN, L.C.; BESENBRUCH, G.E.; HAMILTON, C.J.

2003-01-01

OAK B202 LARGE-SCALE PRODUCTION OF HYDROGEN BY NUCLEAR ENERGY FOR THE HYDROGEN ECONOMY. The ''Hydrogen Economy'' will reduce petroleum imports and greenhouse gas emissions. However, current commercial hydrogen production processes use fossil fuels and releases carbon dioxide. Hydrogen produced from nuclear energy could avoid these concerns. The authors have recently completed a three-year project for the US Department of Energy whose objective was to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the energy source''. Thermochemical water-splitting, a chemical process that accomplishes the decomposition of water into hydrogen and oxygen, met this objective. The goal of the first phase of this study was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen and to select one for further detailed consideration. The authors selected the Sulfur-Iodine cycle, In the second phase, they reviewed all the basic reactor types for suitability to provide the high temperature heat needed by the selected thermochemical water splitting cycle and chose the helium gas-cooled reactor. In the third phase they designed the chemical flowsheet for the thermochemical process and estimated the efficiency and cost of the process and the projected cost of producing hydrogen. These results are summarized in this paper

Nuclear fuel particle and method of production

International Nuclear Information System (INIS)

Wagner-Loffler, M.

1975-01-01

The core consisting of fuel oxide (UO 2 or Th or Pu oxide) of a fuel particle coated with carbon-contained material is enriched with a small addition (max 6 wt.%) of a Ba or Sr compound (atomic ratio for nuclear fuel oxide Ba being 5 - 10 : 1) which is to prevent fission products breaking the protective carbon and/or silicon carbide coating; the Ba or Sr molybdate generated is to reduce the pressure of the carbon dioxide produced. Methods to manufacture such nuclear fuel particles are proposed where 1) an agglomerisation and shaping of the spheres in a fast cycling bowle and 2) a formation of drops from a colloidal solution which are made to congeal in a liquid paraffin column, take place followed by the pyrolytic coating of the particles. (UWI/LH) [de

Reduction of product platform complexity by vectorial Euclidean algorithm

International Nuclear Information System (INIS)

Navarrete, Israel Aguilera; Guzman, Alejandro A. Lozano

2013-01-01

In traditional machine, equipment and devices design, technical solutions are practically independent, thus increasing designs cost and complexity. Overcoming this situation has been tackled just using designer's experience. In this work, a product platform complexity reduction is presented based on a matrix representation of technical solutions versus product properties. This matrix represents the product platform. From this matrix, the Euclidean distances among technical solutions are obtained. Thus, the vectorial distances among technical solutions are identified in a new matrix of order of the number of technical solutions identified. This new matrix can be reorganized in groups with a hierarchical structure, in such a way that modular design of products is now more tractable. As a result of this procedure, the minimum vector distances are found thus being possible to identify the best technical solutions for the design problem raised. Application of these concepts is shown with two examples.

Cost Evaluation with G4-ECONS Program for SI based Nuclear Hydrogen Production Plant

International Nuclear Information System (INIS)

Kim, Jong-ho; Lee, Ki-young; Kim, Yong-wan

2014-01-01

Contemporary hydrogen is production is primarily based on fossil fuels, which is not considered as environments friendly and economically efficient. To achieve the hydrogen economy, it is very important to produce a massive amount of hydrogen in a clean, safe and efficient way. Nuclear production of hydrogen would allow massive production of hydrogen at economic prices while avoiding environments pollution reducing the release of carbon dioxide. Nuclear production of hydrogen could thus become the enabling technology for the hydrogen economy. The economic assessment was performed for nuclear hydrogen production plant consisting of VHTR coupled with SI cycle. For the study, G4-ECONS developed by EMWG of GIF was appropriately modified to calculate the LUHC, assuming 36 months of plant construction time, 5 % of annual interest rate and 12.6 % of fixed charge rate. In G4-ECONS program, LUHC is calculated by the following formula; LUHC = (Annualized TCIC + Annualized O-M Cost + Annualized Fuel Cycle Cost + Annualized D-D Cost) / Annual Hydrogen Production Rate

Energetics of Transport through the Nuclear Pore Complex.

Directory of Open Access Journals (Sweden)

Ali Ghavami

Full Text Available Molecular transport across the nuclear envelope in eukaryotic cells is solely controlled by the nuclear pore complex (NPC. The NPC provides two types of nucleocytoplasmic transport: passive diffusion of small molecules and active chaperon-mediated translocation of large molecules. It has been shown that the interaction between intrinsically disordered proteins that line the central channel of the NPC and the transporting cargoes is the determining factor, but the exact mechanism of transport is yet unknown. Here, we use coarse-grained molecular dynamics simulations to quantify the energy barrier that has to be overcome for molecules to pass through the NPC. We focus on two aspects of transport. First, the passive transport of model cargo molecules with different sizes is studied and the size selectivity feature of the NPC is investigated. Our results show that the transport probability of cargoes is significantly reduced when they are larger than ∼5 nm in diameter. Secondly, we show that incorporating hydrophobic binding spots on the surface of the cargo effectively decreases the energy barrier of the pore. Finally, a simple transport model is proposed which characterizes the energy barrier of the NPC as a function of diameter and hydrophobicity of the transporting particles.

Hydrogen co-production from subcritical water-cooled nuclear power plants in Canada

Energy Technology Data Exchange (ETDEWEB)

Gnanapragasam, N.; Ryland, D.; Suppiah, S., E-mail: gnanapragasamn@aecl.ca [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

2013-06-15

Subcritical water-cooled nuclear reactors (Sub-WCR) operate in several countries including Canada providing electricity to the civilian population. The high-temperature-steam-electrolysis process (HTSEP) is a feasible and laboratory-demonstrated large-scale hydrogen-production process. The thermal and electrical integration of the HTSEP with Sub-WCR-based nuclear-power plants (NPPs) is compared for best integration point, HTSEP operating condition and hydrogen production rate based on thermal energy efficiency. Analysis on integrated thermal efficiency suggests that the Sub-WCR NPP is ideal for hydrogen co-production with a combined efficiency of 36%. HTSEP operation analysis suggests that higher product hydrogen pressure reduces hydrogen and integrated efficiencies. The best integration point for the HTSEP with Sub-WCR NPP is upstream of the high-pressure turbine. (author)

Mechanism of management of competitiveness of production of agrarian and industrial complex

Directory of Open Access Journals (Sweden)

Buryak E. A.

2016-04-01

Full Text Available the concept of competitiveness and mechanisms of management of competitiveness of production is considered. Major factors of ensuring competitiveness of production of agrarian and industrial complex are allocated. The main problems of production of wheat in the Republic of Crimea making negative impact on the level of her competitiveness are revealed. The mechanism of management of competitiveness of production of agrarian and industrial complex is developed.

Countermeasures for dairy products in nuclear emergencies

International Nuclear Information System (INIS)

Sinkko, K.; Ammann, M.; Kostiainen, E.; Salo, A.; Liskola, K.; Haemaelaeinen, R.P.; Mustajoki, J.

2001-01-01

This work was performed in order to plan countermeasures that, after an accidental release of radioactivity, could reduce the dose to the public due to the consumption of contaminated milk and milk products. The attention was focused on whether there are justified and optimised actions below the international recommended concentration levels in foodstuffs. The analysis was conducted as a case study, i.e., it was assumed that a hypothetical accident had happened in a nuclear power plant leading to a release of radionuclides which severely contaminated a wide area of Ostrobothnia, one of Finland's most important milk production areas. The dose averted by actions, the' monetary costs and the feasibility of actions were assessed. It was also studied what information is needed by decision-makers and in which form this information should be presented. Finally, it was examined how planning of countermeasures could be enhanced by applying decision analysis in establishing actions strategies and valuing attributes considered in decision making. Preparative meetings and a concluding workshop was arranged and all authorities involved in food-related emergency management were invited to jointly analyse different options. According to the query made the participants considered the decision workshop and decision analysis very practicable in exercises. The exercise as a whole was also evaluated useful or very useful. The presented techniques in a real situation were considered applicable but not as useful as in exercises. Thus it can be deduced that the concluding workshop and decision analysis interviews augment well conventional emergency exercises. Realistic dose assessments proved out to be very difficult. The software used was able to calculate the maximum radionuclide concentrations in foodstuffs processed from local raw materials. Radionuclide concentration in food or feedstuffs may, however, change quickly. Also, the production and processing of foodstuffs is a complex

Simulation of nuclear plant operation into a stochastic energy production model

International Nuclear Information System (INIS)

Pacheco, R.L.

1983-04-01

A simulation model of nuclear plant operation is developed to fit into a stochastic energy production model. In order to improve the stochastic model used, and also reduce its computational time burdened by the aggregation of the model of nuclear plant operation, a study of tail truncation of the unsupplied demand distribution function has been performed. (E.G.) [pt

The Nuclear Cap-Binding Complex Mediates Meiotic Silencing by Unpaired DNA

Directory of Open Access Journals (Sweden)

Logan M. Decker

2017-04-01

Full Text Available In the filamentous fungus Neurospora crassa, cross walls between individual cells are normally incomplete, making the entire fungal network vulnerable to attack by viruses and selfish DNAs. Accordingly, several genome surveillance mechanisms are maintained to help the fungus combat these repetitive elements. One of these defense mechanisms is called meiotic silencing by unpaired DNA (MSUD, which identifies and silences unpaired genes during meiosis. Utilizing common RNA interference (RNAi proteins, such as Dicer and Argonaute, MSUD targets mRNAs homologous to the unpaired sequence to achieve silencing. In this study, we have identified an additional silencing component, namely the cap-binding complex (CBC. Made up of cap-binding proteins CBP20 and CBP80, CBC associates with the 5′ cap of mRNA transcripts in eukaryotes. The loss of CBC leads to a deficiency in MSUD activity, suggesting its role in mediating silencing. As confirmed in this study, CBC is predominantly nuclear, although it is known to travel in and out of the nucleus to facilitate RNA transport. As seen in animals but not in plants, CBP20’s robust nuclear import depends on CBP80 in Neurospora. CBC interacts with a component (Argonaute of the perinuclear meiotic silencing complex (MSC, directly linking the two cellular factors.

Design of containment system of nuclear fuel attacked by corrosion with leaking fission products

International Nuclear Information System (INIS)

Poblete Maturana, Tomas

2015-01-01

The following report presents the design of an innovative confinement system for the nuclear fuel attacked by corrosion, with leakage of fission products to be used in the RECH-1 nuclear experimental reactor of the Chilean Nuclear Energy Commission, is currently within the framework of the international nuclear waste management program developed by the member countries of the IAEA, including Chile. The main objective of this project is the development of a system that is capable of containing, in the smallest possible volume, the fission products that are released to the reactor coolant medium from the nuclear fuel that are attacked by corrosion. Among the tasks carried out for the development of the project are: the compilation of the necessary bibliography for the selection of the most suitable technology for the retention of the fission products, the calculation of the most important parameters to ensure that the system will operate within ranges that do not compromise the radiological safety, and the design of the hydraulic circuit of the system. The results obtained from the calculations showed that the fuel element confinement system is stable from a thermal point of view since the refrigerant does not under any circumstances reach the saturation temperature and, in addition, from a hydraulic point of view, since the rate at which the refrigerant flows through the hydraulic circuit is low enough so that the deformation of the fuel plates forming the nuclear fuel does not occur. The most appropriate technology for the extraction of fission products according to the literature consulted is by ion exchange. The calculations developed showed that with a very small volume of resins, it is possible to capture all of the non-volatile fission products of a nuclear fuel

Nuclear distributions of NUP62 and NUP214 suggest architectural diversity and spatial patterning among nuclear pore complexes.

Directory of Open Access Journals (Sweden)

Yayoi Kinoshita

Full Text Available The shape of nuclei in many adherent cultured cells approximates an oblate ellipsoid, with contralateral flattened surfaces facing the culture plate or the medium. Observations of cultured cell nuclei from orthogonal perspectives revealed that nucleoporin p62 (NUP62 and nucleoporin 214 (NUP214 are differentially distributed between nuclear pore complexes on the flattened surfaces and peripheral rim of the nucleus. High resolution stimulated emission depletion (STED immunofluorescence microscopy resolved individual NPCs, and suggested both heterogeneity and microheterogeneity in NUP62 and NUP214 immunolabeling among in NPC populations. Similar to nuclear domains and interphase chromosome territories, architectural diversity and spatial patterning of NPCs may be an intrinsic property of the nucleus that is linked to the functions and organization of underlying chromatin.

Fission product release during MCCI. CEC nuclear safety program: MCCI project

Energy Technology Data Exchange (ETDEWEB)

Cenerino, G [CEA Centre d` Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire; Cordfunke, E H.P. [Netherlands Energy Research Foundation (ECN), Petten (Netherlands); Hunterlaar, M E [Netherlands Energy Research Foundation (ECN), Petten (Netherlands)

1995-01-01

The assessment of the consequences of severe accidents in nuclear reactors involving molten core-concrete interactions (MCCls) requires estimates of the quantities and physicochemical forms of the radioactive species released from the melt into the cavity atmosphere. Such estimates in turn require a detailed knowledge of the complex chemical interactions which would occur between the fission products, fuel and the components of the core structural materials and the concrete. In recent years, effort has been put into the thermodynamic characterization of these processes. The results of such studies are important for predicting several aspects of MCCls, including: 1. The release of species by vaporization; 2. the extent of concrete penetration: a. The melt solidus and liquidus temperatures, which in turn affect the heat transfer processes and hence tile predictions of the melt temperature and the onset of solidification, b. the amounts of the solid and liquid phases and the respective compositions, which determines the viscosity of the melt, and c. the composition of the crust formed following the addition of water to quench the interaction. d. the distribution of fission products among metallic and oxidic phases. This SOAR is devoted to thermochemical calculations in the context of MCCI where most fission products and the metallic components of the melt are transferred into an oxidic form sooner or later. Calculations on fission product release from a molten pool without MCCI are underway in the source term project of the CEC-RCA. The following conditions have to be taken into account in order to be able to perform reliable thermodynamic calculations. (orig./HP).

Fission product release during MCCI. CEC nuclear safety program: MCCI project

International Nuclear Information System (INIS)

Cenerino, G.; Hunterlaar, M.E.

1995-01-01

The assessment of the consequences of severe accidents in nuclear reactors involving molten core-concrete interactions (MCCls) requires estimates of the quantities and physicochemical forms of the radioactive species released from the melt into the cavity atmosphere. Such estimates in turn require a detailed knowledge of the complex chemical interactions which would occur between the fission products, fuel and the components of the core structural materials and the concrete. In recent years, effort has been put into the thermodynamic characterization of these processes. The results of such studies are important for predicting several aspects of MCCls, including: 1. The release of species by vaporization; 2. the extent of concrete penetration: a. The melt solidus and liquidus temperatures, which in turn affect the heat transfer processes and hence tile predictions of the melt temperature and the onset of solidification, b. the amounts of the solid and liquid phases and the respective compositions, which determines the viscosity of the melt, and c. the composition of the crust formed following the addition of water to quench the interaction. d. the distribution of fission products among metallic and oxidic phases. This SOAR is devoted to thermochemical calculations in the context of MCCI where most fission products and the metallic components of the melt are transferred into an oxidic form sooner or later. Calculations on fission product release from a molten pool without MCCI are underway in the source term project of the CEC-RCA. The following conditions have to be taken into account in order to be able to perform reliable thermodynamic calculations. (orig./HP)

Neurochemical dynamics of acute orofacial pain in the human trigeminal brainstem nuclear complex.

Science.gov (United States)

de Matos, Nuno M P; Hock, Andreas; Wyss, Michael; Ettlin, Dominik A; Brügger, Mike

2017-11-15

The trigeminal brainstem sensory nuclear complex is the first central relay structure mediating orofacial somatosensory and nociceptive perception. Animal studies suggest a substantial involvement of neurochemical alterations at such basal CNS levels in acute and chronic pain processing. Translating this animal based knowledge to humans is challenging. Human related examining of brainstem functions are challenged by MR related peculiarities as well as applicability aspects of experimentally standardized paradigms. Based on our experience with an MR compatible human orofacial pain model, the aims of the present study were twofold: 1) from a technical perspective, the evaluation of proton magnetic resonance spectroscopy at 3 T regarding measurement accuracy of neurochemical profiles in this small brainstem nuclear complex and 2) the examination of possible neurochemical alterations induced by an experimental orofacial pain model. Data from 13 healthy volunteers aged 19-46 years were analyzed and revealed high quality spectra with significant reductions in total N-acetylaspartate (N-acetylaspartate + N-acetylaspartylglutamate) (-3.7%, p = 0.009) and GABA (-10.88%, p = 0.041) during the pain condition. These results might reflect contributions of N-acetylaspartate and N-acetylaspartylglutamate in neuronal activity-dependent physiologic processes and/or excitatory neurotransmission, whereas changes in GABA might indicate towards a reduction in tonic GABAergic functioning during nociceptive signaling. Summarized, the present study indicates the applicability of 1 H-MRS to obtain neurochemical dynamics within the human trigeminal brainstem sensory nuclear complex. Further developments are needed to pave the way towards bridging important animal based knowledge with human research to understand the neurochemistry of orofacial nociception and pain. Copyright © 2017 Elsevier Inc. All rights reserved.

Fission product chemistry in severe nuclear reactor accidents

International Nuclear Information System (INIS)

Nichols, A.L.

1990-09-01

A specialist's meeting was held at JRC-Ispra from 15 to 17 January 1990 to review the current understanding of fission-product chemistry during severe accidents in light water reactors. Discussions focussed on the important chemical phenomena that could occur across the wide range of conditions of a damaged nuclear plant. Recommendations for future chemistry work were made covering the following areas: (a) fuel degradation and fission-product release, (b) transport and attenuation processes in the reactor coolant system, (c) containment chemistry (iodine behaviour and core-concrete interactions)

Tables and figures from JNDC Nuclear Data Library of fission products, version 2

International Nuclear Information System (INIS)

Ihara, Hitoshi

1989-11-01

The content of JNDC (Japanese Nuclear Data Committee) FP (Fission Product) Nuclear Data Library version 2 for 1227 fission products is presented in the form of tables and figures. The library is inclusive of evaluated decay data such as decay constant, Q-value, average energies of beta, gamma and internal conversion electron, spin-parity, branching ratio of each decay mode and fission yield. The neutron capture cross-sections are also contained for 166 nuclides. The mass number of the fission product nuclides ranges from A = 66 to A = 172. (author)

Equipment for nuclear medical centers, production capabilities of Rosatom enterprises

International Nuclear Information System (INIS)

Gavrish, Yu. N.; Koloskov, S. A.; Smirnov, V. P.; Strokach, A. P.

2015-01-01

Analysis of the capabilities of the State Corporation Rosatom enterprises on the development and production of diagnostic and therapeutic equipment for nuclear medicine centers is presented. Prospects of the development of accelerator equipment for the production of a wide range of radioisotope products are shown, and the trends of its development are determined. A comparative analysis of the technical parameters of domestic tomographs and devices for brachytherapy with foreign counterparts is given

Equipment for nuclear medical centers, production capabilities of Rosatom enterprises

Science.gov (United States)

Gavrish, Yu. N.; Koloskov, S. A.; Smirnov, V. P.; Strokach, A. P.

2015-12-01

Analysis of the capabilities of the State Corporation Rosatom enterprises on the development and production of diagnostic and therapeutic equipment for nuclear medicine centers is presented. Prospects of the development of accelerator equipment for the production of a wide range of radioisotope products are shown, and the trends of its development are determined. A comparative analysis of the technical parameters of domestic tomographs and devices for brachytherapy with foreign counterparts is given.

Production of complex particles in low energy spallation and in fragmentation reactions by in-medium random clusterization

International Nuclear Information System (INIS)

Lacroix, D.; Durand, D.

2005-09-01

Rules for in-medium complex particle production in nuclear reactions are proposed. These rules have been implemented in two models to simulate nucleon-nucleus and nucleus-nucleus reactions around the Fermi energy. Our work emphasizes the effect of randomness in cluster formation, the importance of the nucleonic Fermi motion as well as the role of conservation laws. The concepts of total available phase-space and explored phase-space under constraint imposed by the reaction are clarified. The compatibility of experimental observations with a random clusterization is illustrated in a schematic scenario of a proton-nucleus collision. The role of randomness under constraint is also illustrated in the nucleus-nucleus case. (authors)

Equivalence of complex drug products: advances in and challenges for current regulatory frameworks.

Science.gov (United States)

Hussaarts, Leonie; Mühlebach, Stefan; Shah, Vinod P; McNeil, Scott; Borchard, Gerrit; Flühmann, Beat; Weinstein, Vera; Neervannan, Sesha; Griffiths, Elwyn; Jiang, Wenlei; Wolff-Holz, Elena; Crommelin, Daan J A; de Vlieger, Jon S B

2017-11-01

Biotechnology and nanotechnology provide a growing number of innovator-driven complex drug products and their copy versions. Biologics exemplify one category of complex drugs, but there are also nonbiological complex drug products, including many nanomedicines, such as iron-carbohydrate complexes, drug-carrying liposomes or emulsions, and glatiramoids. In this white paper, which stems from a 1-day conference at the New York Academy of Sciences, we discuss regulatory frameworks in use worldwide (e.g., the U.S. Food and Drug Administration, the European Medicines Agency, the World Health Organization) to approve these complex drug products and their follow-on versions. One of the key questions remains how to assess equivalence of these complex products. We identify a number of points for which consensus was found among the stakeholders who were present: scientists from innovator and generic/follow-on companies, academia, and regulatory bodies from different parts of the world. A number of topics requiring follow-up were identified: (1) assessment of critical attributes to establish equivalence for follow-on versions, (2) the need to publish scientific findings in the public domain to further progress in the field, (3) the necessity to develop worldwide consensus regarding nomenclature and labeling of these complex products, and (4) regulatory actions when substandard complex drug products are identified. © 2017 The Authors. Annals of the New York Academy of Sciences published by Wiley Periodicals, Inc. on behalf of New York Academy of Sciences.

Complex products and systems: potential from using lay out platforms

NARCIS (Netherlands)

Halman, Johannes I.M.; Hofer, Adrian P.

2004-01-01

In their quest to manage the complexity of offering greater product variety, firms in many industries are considering platform-based development of product families. Key in this approach is the sharing of components, modules, and other assets across a family of products. Current research indicates

Nuclear Materials Management for the Nevada Test Site (NTS)

International Nuclear Information System (INIS)

Jesse C. Schreiber

2007-01-01

The Nevada Test Site (NTS) has transitioned from its historical role of weapons testing to a broader role that is focused on being a solution to multiple National Nuclear Security Administration (NNSA) challenges and opportunities with nuclear materials for the nation. NTS is supporting other NNSA sites challenged with safe nuclear materials storage and disposition. NNSA, with site involvement, is currently transforming the nuclear stockpile and supporting infrastructure to meet the 2030 vision. Efforts are under way to make the production complex smaller, more consolidated, and more modern. With respect to the nuclear material stockpile, the NNSA sites are currently reducing the complex nuclear material inventory through dispositioning and consolidating nuclear material. This includes moving material from other sites to NTS. State-of-the-art nuclear material management and control practices at NTS are essential for NTS to ensure that these new activities are accomplished in a safe, secure, efficient, and environmentally responsible manner. NTS is aggressively addressing this challenge

Complex programmable logic device based alarm sequencer for nuclear power plants

International Nuclear Information System (INIS)

Khedkar, Ravindra; Solomon, J. Selva; KrishnaKumar, B.

2001-01-01

Complex Programmable Logic Device based Alarm Sequencer is an instrument, which detects alarms, memorizes them and displays the sequences of occurrence of alarms. It caters to sixteen alarm signals and distinguishes the sequence among any two alarms with a time resolution of 1 ms. The system described has been designed for continuous operation in process plants, nuclear power plants etc. The system has been tested and found to be working satisfactorily. (author)

Softness of Nuclear Matter and the Production of Strange Particles in Neutron Stars

Institute of Scientific and Technical Information of China (English)

陈伟; 文德华; 刘良钢

2003-01-01

In the various models, we study the influences of the softness of nuclear matter, the vacuum fluctuation ofnucleons and σ mesons on the production of strange particles in neutron stars. Wefind that the stiffer the nuclear matter is, the more easily the strange particles is produced in neutron stars. The vacuum fluctuation of nucleons has large effect on strange particle production while that of σ meson has little effect on it.

Pion production in relativistic collisions of nuclear drops

International Nuclear Information System (INIS)

Alonso, C.T.; Wilson, J.R.; McAbee, T.L.; Zingman, J.A.

1988-09-01

In a continuation of the long-standing effort of the nuclear physics community to model atomic nuclei as droplets of a specialized nuclear fluid, we have developed a hydrodynamic model for simulating the collisions of heavy nuclei at relativistic speeds. Our model couples ideal relativistic hydrodynamics with a new Monte Carlo treatment of dynamic pion production and tracking. The collective flow for low-energy (200 MeV/N) collisions predicted by this model compares favorably with results from earlier hydrodynamic calculations which used quite different numerical techniques. Our pion predictions at these lower energies appear to differ, however, from the experimental data on pion multiplicities. In this case of ultra-relativistic (200 GeV/N) collisions, our hydrodynamic model has produced baryonic matter distributions which are in reasonable agreement with recent experimental data. These results may shed some light on the sensitivity of relativistic collision data to the nuclear equation of state. 20 refs., 12 figs

The economics of nuclear energy revisited: lessons from the use of a complex technology subject to major accidents

International Nuclear Information System (INIS)

Finon, D.

2012-01-01

The Fukushima accident again raises the issue of the social and economic viability of nuclear technology. To reassess this viability, we analyze the methods used to internalize the external costs of nuclear energy. These have over time become increasingly complex technologically and specifically affected by major accidents. This combination has served to upset the classical learning curve, calling into question nuclear cost base, social acceptance in the face of climate change and profitability for investors. It has become essential to put in place independent institutions to regulate the safety aspect of nuclear technology and these form a hindrance to its standardization, in turn affecting competitiveness. Nevertheless, the paper argues that the new sequence of internalization of external costs triggered by Fukushima will have limited effects on overall costs, because of previous measures already taken to improve safety. The complexity of nuclear technology is reaching its asymptote: the challenge of 'learning from major accidents' will decrease. On the other hand, the independence and competence of nuclear safety authorities in all countries must be revamped to maximize safety and minimize residual risks. This cannot just be done by decree. However, it is the only way to preserve this global public good - the social acceptance of nuclear technology

Complexity of Products of Some Complete and Complete Bipartite Graphs

Directory of Open Access Journals (Sweden)

S. N. Daoud

2013-01-01

Full Text Available The number of spanning trees in graphs (networks is an important invariant; it is also an important measure of reliability of a network. In this paper, we derive simple formulas of the complexity, number of spanning trees, of products of some complete and complete bipartite graphs such as cartesian product, normal product, composition product, tensor product, and symmetric product, using linear algebra and matrix analysis techniques.

Estimating plutonium production fron long-lived radionuclides in permanent structural components of production reactor cores

International Nuclear Information System (INIS)

Fetter, S.

1992-01-01

This paper reports that the United States and the Soviet Union face critical decisions about the future of plutonium production for nuclear weapons. Both countries could eliminate the economic burden of rebuilding their production complexes by agreeing to ban the production of plutonium for weapons. Such an agreement could also provide important national-security benefits by reinforcing the Non-Proliferation Treaty and by diminishing the ability of both nations to break out of nuclear-arms reduction agreements at a later time - especially if the plutonium in the warheads eliminated by the arms reduction agreements is put under safeguards. A production cutoff would be verifiable

Efficiency and cost advantages of an advanced-technology nuclear electrolytic hydrogen-energy production facility

Science.gov (United States)

Donakowski, T. D.; Escher, W. J. D.; Gregory, D. P.

1977-01-01

The concept of an advanced-technology (viz., 1985 technology) nuclear-electrolytic water electrolysis facility was assessed for hydrogen production cost and efficiency expectations. The facility integrates (1) a high-temperature gas-cooled nuclear reactor (HTGR) operating a binary work cycle, (2) direct-current (d-c) electricity generation via acyclic generators, and (3) high-current-density, high-pressure electrolyzers using a solid polymer electrolyte (SPE). All subsystems are close-coupled and optimally interfaced for hydrogen production alone (i.e., without separate production of electrical power). Pipeline-pressure hydrogen and oxygen are produced at 6900 kPa (1000 psi). We found that this advanced facility would produce hydrogen at costs that were approximately half those associated with contemporary-technology nuclear electrolysis: $5.36 versus $10.86/million Btu, respectively. The nuclear-heat-to-hydrogen-energy conversion efficiency for the advanced system was estimated as 43%, versus 25% for the contemporary system.

Nuclear geometry effect and transport coefficient in semi-inclusive lepton-production of hadrons off nuclei

Directory of Open Access Journals (Sweden)

Na Liu

2015-10-01

Full Text Available Hadron production in semi-inclusive deep-inelastic scattering of leptons from nuclei is an ideal tool to determine and constrain the transport coefficient in cold nuclear matter. The leading-order computations for hadron multiplicity ratios are performed by means of the SW quenching weights and the analytic parameterizations of quenching weights based on BDMPS formalism. The theoretical results are compared to the HERMES positively charged pions production data with the quarks hadronization occurring outside the nucleus. With considering the nuclear geometry effect on hadron production, our predictions are in good agreement with the experimental measurements. The extracted transport parameter from the global fit is shown to be qˆ=0.74±0.03 GeV2/fm for the SW quenching weight without the finite energy corrections. As for the analytic parameterization of BDMPS quenching weight without the quark energy E dependence, the computed transport coefficient is qˆ=0.20±0.02 GeV2/fm. It is found that the nuclear geometry effect has a significant impact on the transport coefficient in cold nuclear matter. It is necessary to consider the detailed nuclear geometry in studying the semi-inclusive hadron production in deep inelastic scattering on nuclear targets.

Z Production as a Test of Nuclear Effects at the LHC

CERN Document Server

Zhang, X; Zhang, Xiaofei; Fai, George

2002-01-01

We predict the Z transverse momentum distribution from proton-proton and nuclear collisions at the LHC. After demonstrating that higher-twist nuclear effects are very small, we propose $Z^0$ production as a precision test for leading-twist pQCD in the TeV energy region. We also point out that shadowing may result in unexpected phenomenology at the LHC.

Computationally-generated nuclear forensic characteristics of early production reactors with an emphasis on sensitivity and uncertainty

International Nuclear Information System (INIS)

Redd, Evan M.; Sjoden, Glenn; Erickson, Anna

2017-01-01

Highlights: •X-10 reactor is used as a case study for nuclear forensic signatures. •S/U analysis is conducted to derive statistically relevant markers. •Computationally-generated signatures aid with proliferation pathway identification. •Highest uncertainty in total plutonium production originates from 238 Pu and 242 Pu. -- Abstract: With nuclear technology and analysis advancements, site access restrictions, and ban on nuclear testing, computationally-generated nuclear forensic signatures are becoming more important in gaining knowledge to a reclusive country’s weapon material production capabilities. In particular, graphite-moderated reactors provide an appropriate case study for isotopics relevant in Pu production in a clandestine nuclear program due to the ease of design and low thermal output. We study the production characteristics of the X-10 reactor with a goal to develop statistically-relevant nuclear forensic signatures from early Pu production. In X-10 reactor, a flat flux gradient and low burnup produce exceptionally pure Pu as evident by the 240 Pu/ 239 Pu ratio. However, these design aspects also make determining reactor zone attribution, done with the 242 Pu/ 240 Pu ratio, uncertain. Alternatively, the same ratios produce statistically differentiable results between Manhattan Project and post-Manhattan Project reactor configurations, allowing for attribution conclusions.

Polymer brushes infiltrated by nanoparticles and applications to the nuclear pore complex

Science.gov (United States)

Opferman, Michael G.

Systems of grafted polymers in the presence of additives are useful in a variety of contexts including industrial applications, solar cells, organic electronics, drug delivery, and nucleocytoplasmic transport. In this thesis, we will consider the morphologies that polymer brushes attain when exposed to a solution of additives (which we generically term "nanoparticles"), particularly when those nanparticles interact attractively with the polymers. We find that nanoparticles of this type can have a dramatic effect on the height of the polymer chains above the grafting surface, and they can induce highly non-uniform morphologies, including ones in which a dense layer of nanoparticles and monomers forms near the grafting surface. We consider especially the relevance of the system to several experiments performed on biopolymers in the nuclear pore complex when they interact attractively with transport factors that regulate nucleocytoplasmic transport. We find that, although these experiments appear to give inconsistent results, the inconsistencies can be reconciled through two simple models: the Alexander-de Gennes polymer brush, and the Milner-Witten-Cates polymer brush. Our findings should contribute to the understanding of the nuclear pore complex in that experiments can be better understood in the context of their relevant control parameters.

Hybrid systems to address seasonal mismatches between electricity production and demand in nuclear renewable electrical grids

International Nuclear Information System (INIS)

Forsberg, Charles

2013-01-01

A strategy to enable zero-carbon variable electricity production with full utilization of renewable and nuclear energy sources has been developed. Wind and solar systems send electricity to the grid. Nuclear plants operate at full capacity with variable steam to turbines to match electricity demand with production (renewables and nuclear). Excess steam at times of low electricity prices and electricity demand go to hybrid fuel production and storage systems. The characteristic of these hybrid technologies is that the economic penalties for variable nuclear steam inputs are small. Three hybrid systems were identified that could be deployed at the required scale. The first option is the gigawatt-year hourly-to-seasonal heat storage system where excess steam from the nuclear plant is used to heat rock a kilometer underground to create an artificial geothermal heat source. The heat source produces electricity on demand using geothermal technology. The second option uses steam from the nuclear plant and electricity from the grid with high-temperature electrolysis (HTR) cells to produce hydrogen and oxygen. Hydrogen is primarily for industrial applications; however, the HTE can be operated in reverse using hydrogen for peak electricity production. The third option uses variable steam and electricity for shale oil production. -- Highlights: •A system is proposed to meet variable hourly to seasonal electricity demand. •Variable solar and wind electricity sent to the grid. •Base-load nuclear plants send variable steam for electricity and hybrid systems. •Hybrid energy systems can economically absorb gigawatts of variable steam. •Hybrid systems include geothermal heat storage, hydrogen, and shale-oil production

Channel Nucleoporins Recruit PLK-1 to Nuclear Pore Complexes to Direct Nuclear Envelope Breakdown in C. elegans.

Science.gov (United States)

Martino, Lisa; Morchoisne-Bolhy, Stéphanie; Cheerambathur, Dhanya K; Van Hove, Lucie; Dumont, Julien; Joly, Nicolas; Desai, Arshad; Doye, Valérie; Pintard, Lionel

2017-10-23

In animal cells, nuclear envelope breakdown (NEBD) is required for proper chromosome segregation. Whereas mitotic kinases have been implicated in NEBD, how they coordinate their activity to trigger this event is unclear. Here, we show that both in human cells and Caenorhabditis elegans, the Polo-like kinase 1 (PLK-1) is recruited to the nuclear pore complexes, just prior to NEBD, through its Polo-box domain (PBD). We provide evidence that PLK-1 localization to the nuclear envelope (NE) is required for efficient NEBD. We identify the central channel nucleoporins NPP-1/Nup58, NPP-4/Nup54, and NPP-11/Nup62 as the critical factors anchoring PLK-1 to the NE in C. elegans. In particular, NPP-1, NPP-4, and NPP-11 primed at multiple Polo-docking sites by Cdk1 and PLK-1 itself physically interact with the PLK-1 PBD. We conclude that nucleoporins play an unanticipated regulatory role in NEBD, by recruiting PLK-1 to the NE thereby facilitating phosphorylation of critical downstream targets. Copyright © 2017 Elsevier Inc. All rights reserved.

The Possibility Using the Power Production Function of Complex Variable for Economic Forecasting

Directory of Open Access Journals (Sweden)

Sergey Gennadyevich Svetunkov

2016-09-01

Full Text Available The possibility of dynamic analysis and forecasting production results using the power production functions of complex variables with real coefficients is considered. This model expands the arsenal of instrumental methods and allows multivariate production forecasts which are unattainable by other methods of real variables as the functions of complex variables simulate the production differently in comparison with the models of real variables. The values of coefficients of the power production functions of complex variables can be calculated for each statistical observation. This allows to consider the change of the coefficients over time, to analyze this trend and predict the values of the coefficients for a given term, thereby to predict the form of the production function, which forecasts the operating results. Thus, the model of the production function with variable coefficients is introduced into the scientific circulation. With this model, the inverse problem of forecasting might be solved, such as the determination of the necessary quantities of labor and capital to achieve the desired operational results. The study is based on the principles of the modern methodology of complex-valued economy, one of its sections is the complex-valued patterns of production functions. In the article, the possibility of economic forecasting is tested on the example of the UK economy. The results of this prediction are compared with the forecasts obtained by other methods, which have led to the conclusion about the effectiveness of the proposed approach and the method of forecasting at the macro levels of production systems. A complex-valued power model of the production function is recommended for the multivariate prediction of sustainable production systems — the global economy, the economies of individual countries, major industries and regions.

Fast accelerator driven subcritical system for energy production: nuclear fuel evolution

International Nuclear Information System (INIS)

Barros, Graiciany de P.; Pereira, Claubia; Veloso, Maria A.F.; Costa, Antonella L.

2011-01-01

Accelerators Driven Systems (ADS) are an innovative type of nuclear system, which is useful for long-lived fission product transmutation and fuel regeneration. The ADS consist of a coupling of a sub-critical nuclear core reactor and a proton beam produced by a particle accelerator. These particles are injected into a target for the neutrons production by spallation reactions. The neutrons are then used to maintain the fission chain in the sub-critical core. The aim of this study is to investigate the nuclear fuel evolution of a lead cooled accelerator driven system used for energy production. The fuel studied is a mixture based upon "2"3"2Th and "2"3"3U. Since thorium is an abundant fertile material, there is hope for the thorium-cycle fuels for an accelerator driven sub-critical system. The target is a lead spallation target and the core is filled with a hexagonal lattice. High energy neutrons are used to reduce the negative reactivity caused by the presence of protoactinium, since this effect is most pronounced in the thermal range of the neutron spectrum. For that reason, such material is not added moderator to the system. In this work is used the Monte Carlo code MCNPX 2.6.0, that presents the the depletion/ burnup capability. The k_e_f_f evolution, the neutron energy spectrum in the core and the nuclear fuel evolution using ADS source (SDEF) and kcode-mode are evaluated during the burnup. (author)

The fanconi anemia proteins FANCA and FANCG stabilize each other and promote the nuclear accumulation of the Fanconi anemia complex.

Science.gov (United States)

Garcia-Higuera, I; Kuang, Y; Denham, J; D'Andrea, A D

2000-11-01

Fanconi anemia (FA) is an autosomal recessive cancer susceptibility syndrome with 8 complementation groups. Four of the FA genes have been cloned, and at least 3 of the encoded proteins, FANCA, FANCC, and FANCG/XRCC9, interact in a multisubunit protein complex. The FANCG protein binds directly to the amino terminal nuclear localization sequence (NLS) of FANCA, suggesting that FANCG plays a role in regulating FANCA nuclear accumulation. In the current study the functional consequences of FANCG/FANCA binding were examined. Correction of an FA-G cell line with the FANCG complementary DNA (cDNA) resulted in FANCA/FANCG binding, prolongation of the cellular half-life of FANCA, and an increase in the nuclear accumulation of the FA protein complex. Similar results were obtained upon correction of an FA-A cell line, with a reciprocal increase in the half-life of FANCG. Patient-derived mutant forms of FANCA, containing an intact NLS sequence but point mutations in the carboxy-terminal leucine zipper region, bound FANCG in the cytoplasm. The mutant forms failed to translocate to the nucleus of transduced cells, thereby suggesting a model of coordinated binding and nuclear translocation. These results demonstrate that the FANCA/FANCG interaction is required to maintain the cellular levels of both proteins. Moreover, at least one function of FANCG and FANCA is to regulate the nuclear accumulation of the FA protein complex. Failure to accumulate the nuclear FA protein complex results in the characteristic spectrum of clinical and cellular abnormalities observed in FA.

Proceedings of the fourth information exchange meeting on nuclear production of hydrogen

International Nuclear Information System (INIS)

2010-01-01

The use of hydrogen, both as feedstock for the industry (oil and chemical) and as an energy carrier, is expected to grow substantially during the coming decades. The current predominant method of producing hydrogen by steam-reforming methane (from natural gas) is not sustainable and has environmental drawbacks, including the emission of greenhouse gasses (GHGs). Nuclear energy offers a way to produce hydrogen from water without depleting natural gas, a valuable natural resource, and without the emission of GHGs. The OECD Nuclear Energy Agency (NEA) has conducted a number of information exchange meetings with the objective of stimulating progress in the development of nuclear production of hydrogen. These meetings, held in 2000 in Paris, France, in 2003 in Argonne, Illinois, USA, and in 2005 in Oarai, Japan, were well-attended and very successful. It is hoped that the information presented at fourth meeting and contained in these proceedings may be useful in advancing the objective of achieving economically viable, sustainable and emission-free production of hydrogen. The need for a sustainable supply of clean energy is one of the main problems facing the world. Among the various energy technologies which may be considered (including hydro, wind, solar, geo-thermal, wave and tidal), only nuclear - through the use of fast-neutron fission reactors - is capable of delivering the copious quantities of sustainable energy that will be required. In view of this, one of the means under consideration for achieving the objective of nuclear-produced hydrogen is enhanced international cooperation, including the establishment of one or more OECD/NEA joint projects. In this respect, it is worth noting that similar joint projects undertaken in the past (for example, the Dragon Project and the Halden Reactor Project) have been highly beneficial and have provided significant amounts of useful information to the sponsoring countries at shared costs. This report describes the

Fanconi Anemia Proteins FANCA, FANCC, and FANCG/XRCC9 Interact in a Functional Nuclear Complex

OpenAIRE

Garcia-Higuera, Irene; Kuang, Yanan; Näf, Dieter; Wasik, Jennifer; D’Andrea, Alan D.

1999-01-01

Fanconi anemia (FA) is an autosomal recessive cancer susceptibility syndrome with at least eight complementation groups (A to H). Three FA genes, corresponding to complementation groups A, C, and G, have been cloned, but their cellular function remains unknown. We have previously demonstrated that the FANCA and FANCC proteins interact and form a nuclear complex in normal cells, suggesting that the proteins cooperate in a nuclear function. In this report, we demonstrate that the recently clone...

International economic association on production of nuclear instrumentation - ''INTERINSTRUMENT''

International Nuclear Information System (INIS)

Twardon, Z.

1979-01-01

History of establishment and development of the International economic association ''Interinstrument'' is stated. Structure of the Association is given and directions of its activity, as well as structure of its budget. List is given of organizations, performing works according to the agreements with the Association. Main directions are stated of activity of the Association in the field of specialization of production of items of nuclear equipment; co-ordination of activity in the sphere of foreign trade; information about new instruments. Activity is stated of the branch offices of the Association, engaged in maintenance of instruments and nuclear equipment [ru

Cold Nuclear Matter Effects on J/psi Production: Intrinsic and Extrinsic Transverse Momentum Effects

Energy Technology Data Exchange (ETDEWEB)

Ferreiro, E.G.; /Santiago de Compostela U.; Fleuret, F.; /Ecole Polytechnique; Lansberg, J.P.; /Heidelberg U.; Rakotozafindrabe, A.; /SPhN, DAPNIA, Saclay

2010-08-26

Cold nuclear matter effects on J/{psi} production in proton-nucleus and nucleus-nucleus collisions are evaluated taking into account the specific J/{psi}-production kinematics at the partonic level, the shadowing of the initial parton distributions and the absorption in the nuclear matter. We consider two different parton processes for the c{bar c}-pair production: one with collinear gluons and a recoiling gluon in the final state and the other with initial gluons carrying intrinsic transverse momentum. Our results are compared to RHIC observables. The smaller values of the nuclear modification factor R{sub AA} in the forward rapidity region (with respect to the mid rapidity region) are partially explained, therefore potentially reducing the need for recombination effects.

Storage ion trap of an 'In-Flight Capture' type for precise mass measurement of radioactive nuclear reaction products and fission fragments

International Nuclear Information System (INIS)

Tarantin, N.I.

2001-01-01

Data on nuclear masses provide a basis for creating and testing various nuclear models. A tandem system of FLNR comprised of the U-400M cyclotron, the COMBAS magnetic separator and the mass-spectrometric ion trap of an 'in-flight capture' type is considered as a possible complex for producing of the short-lived nuclei in fragmentation reactions by heavy ions and for precise mass measurement of these nuclei. The plan of scientific and technical FLNR research includes a project DRIBs for producing beams of accelerated radioactive nuclear reaction products and photofission fragments. This project proposes also precise mass measurements of the fission fragment with the help of the ion trap. The in-flight entrance of the ions and their capture in the mass-spectrometric ion trap using the monochromatizing degrader, the static electric and magnetic fields and a new invention, a magnetic unidirectional transporting ventil, is considered

Dissecting mechanisms of nuclear mRNA surveillance in THO/sub2 complex mutants

DEFF Research Database (Denmark)

Rougemaille, Mathieu; Gudipati, Rajani K; Olesen, Jens Raabjerg

2007-01-01

The nuclear exosome is involved in numerous RNA metabolic processes. Exosome degradation of rRNA, snoRNA, snRNA and tRNA in Saccharomyces cerevisiae is activated by TRAMP complexes, containing either the Trf4p or Trf5p poly(A) polymerase. These enzymes are presumed to facilitate exosome access...... is required for both retention and degradation of nuclear restricted mRNAs. We show here that Trf4p, in the context of TRAMP, is an mRNA surveillance factor. However, unlike Rrp6p, Trf4p only partakes in RNA degradation and not in transcript retention. Surprisingly, a polyadenylation-defective Trf4p protein...

Bcs1p can rescue a large and productive cytochrome bc(1) complex assembly intermediate in the inner membrane of yeast mitochondria.

Science.gov (United States)

Conte, Laura; Trumpower, Bernard L; Zara, Vincenzo

2011-01-01

The yeast cytochrome bc(1) complex, a component of the mitochondrial respiratory chain, is composed of ten distinct protein subunits. In the assembly of the bc(1) complex, some ancillary proteins, such as the chaperone Bcs1p, are actively involved. The deletion of the nuclear gene encoding this chaperone caused the arrest of the bc(1) assembly and the formation of a functionally inactive bc(1) core structure of about 500-kDa. This immature bc(1) core structure could represent, on the one hand, a true assembly intermediate or, on the other hand, a degradation product and/or an incorrect product of assembly. The experiments here reported show that the gradual expression of Bcs1p in the yeast strain lacking this protein was progressively able to rescue the bc(1) core structure leading to the formation of the functional homodimeric bc(1) complex. Following Bcs1p expression, the mature bc(1) complex was also progressively converted into two supercomplexes with the cytochrome c oxidase complex. The capability of restoring the bc(1) complex and the supercomplexes was also possessed by the mutated yeast R81C Bcsp1. Notably, in the human ortholog BCS1L, the corresponding point mutation (R45C) was instead the cause of a severe bc(1) complex deficiency. Differently from the yeast R81C Bcs1p, two other mutated Bcs1p's (K192P and F401I) were unable to recover the bc(1) core structure in yeast. This study identifies for the first time a productive assembly intermediate of the yeast bc(1) complex and gives new insights into the molecular mechanisms involved in the last steps of bc(1) assembly. Copyright © 2010 Elsevier B.V. All rights reserved.

Inhibitory mechanism of chroman compound on LPS-induced nitric oxide production and nuclear factor-κB activation

International Nuclear Information System (INIS)

Kim, Byung Hak; Reddy, Alavala Matta; Lee, Kum-Ho; Chung, Eun Yong; Cho, Sung Min; Lee, Heesoon; Min, Kyung Rak; Kim, Youngsoo

2004-01-01

6-Hydroxy-7-methoxychroman-2-carboxylic acid phenylamide (KL-1156) is a novel chemically synthetic compound. In the present study, the chroman KL-1156 compound was found to inhibit lipopolysaccharide (LPS)-induced nitric oxide production in macrophages RAW 264.7. KL-1156 compound attenuated LPS-induced synthesis of both mRNA and protein of inducible nitric oxide synthase (iNOS), in parallel, and inhibited LPS-induced iNOS promoter activity, indicating that the chroman compound down-regulated iNOS expression at transcription level. As a mechanism of the anti-inflammatory action shown by KL-1156 compound, suppression of nuclear factor (NF)-κB has been documented. KL-1156 compound exhibited a dose-dependent inhibitory effect on LPS-induced NF-κB transcriptional activity in macrophages RAW 264.7. Furthermore, the compound inhibited LPS-induced nuclear translocation of NF-κB p65 and DNA binding activity of NF-κB complex, in parallel, but did not affect IκBα degradation. Taken together, this study demonstrated that chroman KL-1156 compound interfered with nuclear translocation step of NF-κB p65, which was attributable to its anti-inflammatory action

The Jules Horowitz nuclear complex a plat-form for research and development on nuclear fuel and materials for the 21st century

International Nuclear Information System (INIS)

Ballagny, A.; Bouilloux, Y.; Chantoin, P.; Iracane, D.

2001-01-01

The CEA intends to build a material test reactor at Cadarache (South of France). This reactor would be the central piece of a wider complex which would include experimental fuel fabrication, destructive and non destructive examinations, in-reactor on line measurement advanced methods and modelling. For 50 years this platform would provide the necessary knowledge to the nuclear industry, the safety authority and to the national decision makers. This material test reactor called Jules Horowitz reactor (JHR) could be a key facility for industry and the central component of the European research area on nuclear fission from 2010. In this paper an overview of the research complex is given and a first approach of the development effort undertaken to meet the requirements in term of : ''time to result, experimental cost, experiment quality and international co-operation. Finally are given several ways of technical development undertaken to meet the above requirements. (orig.)

Environmental Restoration Strategic Plan. Remediating the nuclear weapons complex

International Nuclear Information System (INIS)

1995-08-01

With the end of the cold war, the US has a reduced need for nuclear weapons production. In response, the Department of Energy has redirected resources from weapons production to weapons dismantlement and environmental remediation. To this end, in November 1989, the US Department of Energy (DOE) established the Office of Environmental Restoration and Waste Management (renamed the Office of Environmental Management in 1994). It was created to bring under a central authority the management of radioactive and hazardous wastes at DOE sites and inactive or shut down facilities. The Environmental Restoration Program, a major component of DOE's Environmental Management Program, is responsible for the remediation and management of contaminated environmental media (e.g., soil, groundwater, sediments) and the decommissioning of facilities and structures at 130 sites in over 30 states and territories

Risk management and nuclear human resources management in construction nuclear power plants in the Gulf Countries

International Nuclear Information System (INIS)

Saeed Hakami; Salim Almarmary

2009-01-01

The countries of the Gulf region have the capacity to rapidly expand their economic growth and gross domestic product (GDP). Also, one may observe that their growth rate is very high. To match this, they need a mix of energy sources for this economic growth. Nuclear power plants can have a significant role as a source of energy in the Gulf countries. Although, some of the Gulf countries signed contracts to construct nuclear power plants, they still require high a level of education as well as sufficient and adequate human resources in order to solve complex issues which may happen at nuclear power plants. The objective of this paper is to identify the complex issues that may arise at a nuclear site. Then the paper goes on to discuss how to evaluate these issues. Finally, the paper studies how to manage and control such complex issues in the work place. The advantage of highly educated people as well as sufficient and adequate human resource can increasingly protect and save human health and the natural environment from issues relating to the use of nuclear energy. There are vast theories, strategies and tools that have discussed in regards to human resources management in the nuclear industries. However, this paper chiefly provides a new risk management methodology. This methodology helps to highlight the risk factors and their consequences at nuclear sites. This paper is intended to decrease risks; to protect human health in the work place at nuclear power plants and save the environment within and beyond national borders and for future generations. It aims to increase safety from the use of nuclear energy, particularly in the Gulf countries.(Author)

Nuclear systems of level measurement

International Nuclear Information System (INIS)

Lara, A.J.; Cabrera, M.J.

1992-01-01

In the industry there are processes in which is necessary to maintain the products level controlled which are handled for their transformation. The majority of such processes and by the operation conditions, they do not admit measure systems of level of invasive type then the application of nuclear techniques for level measurement results a big aid in these cases, since all the system installation is situated beyond frontiers of vessels that contain the product for measuring. In the Department of Nuclear Technology Applications of Mexican Petroleum Institute was developed a level measurement system by gamma rays transmission which operates in the Low Density Polyethylene plant of Petrochemical Complex Escolin at Poza Rica, Veracruz, Mexico. (Author)

Nuclear Material Processing at the Savannah River Site

International Nuclear Information System (INIS)

Severynse, T.F.

1998-07-01

Plutonium production for national defense began at Savannah River in the mid-1950s, following construction of production reactors and separations facilities. Following the successful completion of its production mission, the site's nuclear material processing facilities continue to operate to perform stabilization of excess materials and potentially support the disposition of these materials. A number of restoration and productivity improvement projects implemented in the 1980s, totaling nearly a billion dollars, have resulted in these facilities representing the most modern and only remaining operating large-scale processing facilities in the DOE Complex. Together with the Site's extensive nuclear infrastructure, and integrated waste management system, SRS is the only DOE site with the capability and mission of ongoing processing operations

Crystal structure of the Xpo1p nuclear export complex bound to the SxFG/PxFG repeats of the nucleoporin Nup42p.

Science.gov (United States)

Koyama, Masako; Hirano, Hidemi; Shirai, Natsuki; Matsuura, Yoshiyuki

2017-10-01

Xpo1p (yeast CRM1) is the major nuclear export receptor that carries a plethora of proteins and ribonucleoproteins from the nucleus to cytoplasm. The passage of the Xpo1p nuclear export complex through nuclear pore complexes (NPCs) is facilitated by interactions with nucleoporins (Nups) containing extensive repeats of phenylalanine-glycine (so-called FG repeats), although the precise role of each Nup in the nuclear export reaction remains incompletely understood. Here we report structural and biochemical characterization of the interactions between the Xpo1p nuclear export complex and the FG repeats of Nup42p, a nucleoporin localized at the cytoplasmic face of yeast NPCs and has characteristic SxFG/PxFG sequence repeat motif. The crystal structure of Xpo1p-PKI-Nup42p-Gsp1p-GTP complex identified three binding sites for the SxFG/PxFG repeats on HEAT repeats 14-20 of Xpo1p. Mutational analyses of Nup42p showed that the conserved serines and prolines in the SxFG/PxFG repeats contribute to Xpo1p-Nup42p binding. Our structural and biochemical data suggest that SxFG/PxFG-Nups such as Nup42p and Nup159p at the cytoplasmic face of NPCs provide high-affinity docking sites for the Xpo1p nuclear export complex in the terminal stage of NPC passage and that subsequent disassembly of the nuclear export complex facilitates recycling of free Xpo1p back to the nucleus. © 2017 Molecular Biology Society of Japan and John Wiley & Sons Australia, Ltd.

Relationship between chromatin complexity and nuclear envelope circularity in hippocampal pyramidal neurons

International Nuclear Information System (INIS)

Pantic, Igor; Basailovic, Milos; Paunovic, Jovana; Pantic, Senka

2015-01-01

Highlights: •We analyzed chromatin structure and nuclear envelope of 200 hippocampal pyramidal neurons. •Fractal and GLCM mathematical parameters were calculated each chromatin structure. •Nuclear shape was quantified by calculating circularity of the nuclear envelope. •Circularity was in significant relationship with chromatin fractal dimension. •Strong correlation was detected between circularity and some GLCM parameters. -- Abstract: In this study we tested the existence and strength of the relationship between circularity of nuclear envelope and mathematical parameters of chromatin structure. Coronal sections of the brain were made in 10 male albino mice. The brain tissue was stained using a modification of Feulgen method for DNA visualization. A total of 200 hippocampal pyramidal neurons (20 per animal) were visualized using DEM 200 High-Speed Color CMOS Chip and Olympus CX21FS1 microscope. Circularity of the nuclear membrane was calculated in ImageJ (NIH, USA) after the nuclear segmentation, based on the freehand selection of the nuclear regions of interest. Circularity was determined from the values of area and perimeter. For each chromatin structure, using fractal and grey level co-occurrence matrix (GLCM) algorithms, we determined the values of fractal dimension, lacunarity, angular second moment, GLCM entropy, inverse difference moment, GLCM correlation, and GLCM contrast. It was found that circularity is in a significant correlation (p < 0.05) with fractal dimension as the main parameter of fractal complexity analysis. Also, circularity was in a very strong relationship (p < 0.001) with certain parameters of grey level co-occurrence matrix such as the angular second moment and GLCM correlation. This is the first study to indicate that nuclear shape is significantly related to mathematical parameters of higher chromatin organization. Also, it seems that circularity of the nuclear envelope is a good predictor of certain features of chromatin

Characterization, expression and complex formation of the murine Fanconi anaemia gene product Fancg.

Science.gov (United States)

van de Vrugt, Henri J; Koomen, Mireille; Berns, Mariska A D; de Vries, Yne; Rooimans, Martin A; van der Weel, Laura; Blom, Eric; de Groot, Jan; Schepers, Rik J; Stone, Stacie; Hoatlin, Maureen E; Cheng, Ngan Ching; Joenje, Hans; Arwert, Fré

2002-03-01

Fanconi anaemia (FA) is an autosomal recessive chromosomal instability disorder. Six distinct FA disease genes have been identified, the products of which function in an integrated pathway that is thought to support a nuclear caretaker function. Comparison of FA gene characteristics in different species may help to unravel the molecular function of the FA pathway. We have cloned the murine homologue of the Fanconi anaemia complementation group G gene, FANCG/XRCC9. The murine Fancg protein shows an 83% similarity to the human protein sequence, and has a predicted molecular weight of 68.5 kDa. Expression of mouse Fancg in human FA-G lymphoblasts fully corrects their cross-linker hypersensitivity. At mRNA and protein levels we detected the co-expression of Fancg and Fanca in murine tissues. In addition, mouse Fancg and Fanca proteins co-purify by immunoprecipitation. Upon transfection into Fanca-deficient mouse embryonic fibroblasts EGFP-Fancg chimeric protein was detectable in the nucleus. We identified a murine cDNA, Fancg, which cross-complements the cellular defect of human FA-G cells and thus represents a true homologue of human FANCG. Spleen, thymus and testis showed the highest Fancg expression levels. Although Fancg and Fanca are able to form a complex, this interaction is not required for Fancg to accumulate in the nuclear compartment.

The creation of the analytical information system to serve the process of complex decommissioning of nuclear submarines (NSM) and surface ships (SS) with nuclear power installations (NPI)

International Nuclear Information System (INIS)

Terentiev, V.G.; Yakovlev, N.E.; Tyurin, A.V.

2002-01-01

Management of the decommissioning of nuclear vessels includes information collection, accumulation, systematisation and analysis on the complex utilization of nuclear submarines and surface ships with nuclear power installations and on treatment of spent nuclear fuel and radioactive wastes. The relevant data on radiation and ecology, science and technology, law and economy, administration and management should be properly processed. The general objective of the analytical information system (AIS) development, described in the present paper, is the efficiency upgrading for nuclear submarine utilization management and decision making. The report considers information provision and functioning principles as well as software/hardware solutions associated with the AIS creation. (author)

Determination of aromatic fragment content in phenol-containing fractions of solid fuel conversion products using nuclear magnetic resonance spectroscopy

Energy Technology Data Exchange (ETDEWEB)

Kanitskaya, L.V.; Kushnarev, D.F.; Polonov, V.M.; Kalabin, G.A.

1986-03-01

Optimum conditions are determined for obtaining quantitative nuclear magnetic resonance /sup 13/C spectra of fragments in phenol-containing fraction of coal products. Causes are analyzed of residual signals in spectra of un-protonized carbon atoms. The tests were carried out on: low-temperature carbonization tar and phenol fraction obtained during medium-temperature coking of Cherenkhovskii coal (which contains 84.13% C; 9.68% H; 1.23% S; 4.96% O); products of tar hydrogenation with various phenol content; standard phenol mixture. It was found that quantitative determination of aromatic fraction content in coal conversion products and other phenol- and amine-containing complex mixtures, using NMR spectroscopy requires the addition of dimethylsulfide or acetone in order to suppress specific interactions of phenols (amines) with relaxants and obtain quantitative subspectra of Tertiary and Quaternary aromatic carbon atoms. 16 references.

Biomechanics of the transport barrier in the nuclear pore complex.

Science.gov (United States)

Stanley, George J; Fassati, Ariberto; Hoogenboom, Bart W

2017-08-01

The nuclear pore complex (NPC) is the selective gateway through which all molecules must pass when entering or exiting the nucleus. It is a cog in the gene expression pathway, an entrance to the nucleus exploited by viruses, and a highly-tuned nanoscale filter. The NPC is a large proteinaceous assembly with a central lumen occluded by natively disordered proteins, known as FG-nucleoporins (or FG-nups). These FG-nups, along with a family of soluble proteins known as nuclear transport receptors (NTRs), form the selective transport barrier. Although much is known about the transport cycle and the necessity of NTRs for chaperoning cargo molecules through the NPC, the mechanism by which NTRs and NTR•cargo complexes translocate the selective transport barrier is not well understood. How can disordered FG-nups and soluble NTRs form a transport barrier that is selective, ATP-free, and fast? In this work, we review various mechanical approaches - both experimental and theoretical/computational - employed to better understand the morphology of the FG-nups, and their role in nucleocytoplasmic transport. Recent experiments on FG-nups tethered to planar surfaces, coupled with quantitative modelling work suggests that FG-nup morphologies are the result of a finely balanced system with significant contributions from FG-nup cohesiveness and entropic repulsion, and from NTR•FG-nup binding avidity; whilst AFM experiments on intact NPCs suggest that the FG-nups are sufficiently cohesive to form condensates in the centre of the NPC lumen, which may transiently dissolve to facilitate the transport of larger cargoes. Copyright © 2017 Elsevier Ltd. All rights reserved.

Actinide separation chemistry in nuclear waste streams, an OECD Nuclear Energy Agency review

International Nuclear Information System (INIS)

Madic, C.

1997-01-01

The separation of actinide elements from various waste materials, either produced in nuclear fuel cycle or in the past during nuclear weapon production, represent a significant issue facing developed countries. Improvements in the efficiencies of the separation processes can be expected from a better knowledge of the chemistry of these elements in these complex matrices. The Nuclear Science Committee of the OECD/NEA has established a task force of experts in actinide chemistry to review the current and developing separation techniques and chemical processes. Recommendations were made for future research and development programs. This article presents briefly the work of the Task Force which will be published soon as an OECD/NEA/NSC Report. (author)

Stem Complexity and Inflectional Encoding in Language Production

NARCIS (Netherlands)

Janssen, D.P.; Roelofs, A.P.A.; Levelt, W.J.M.

2004-01-01

Three experiments are reported that examined whether stem complexity plays a role in inflecting polymorphemic words in language production. Experiment 1 showed that preparation effects for words with polymorphemic stems are larger when they are produced among words with constant inflectional

Radiological and environmental safety aspects of uranium fuel fabrication plants at Nuclear Fuel Complex, Hyderabad

International Nuclear Information System (INIS)

Viswanathan, S.; Surya Rao, B.; Lakshmanan, A.R.; Krishna Rao, T.

1991-01-01

Nuclear Fuel Complex, Hyderabad manufactures uranium dioxide fuel assemblies for PHWRs and BWRs operating in India. Starting materials are magnesium diuranate received from UCIL, Jaduguda and imported UF. Both of these are converted to UO 2 pellets by identical chemical processes and mechanical compacting. Since the uranium handled here is free of daughter product activities, external radiation is not a problem. Inhalation of airborne U compounds is one of the main source of exposure. Engineered protective measures like enclosures around U bearing powder handling equipment and local exhausts reduce worker's exposure. Installation of pre-filters, wet rotoclones and electrostatic precipitators in the ventillation system reduces the release of U into the environment. The criticality hazard in handling slightly enriched uranium is very low due to the built-in control based on geometry and inventory. Where airborne uranium is significant, workers are provided with protective respirators. The workers are regularly monitored for external exposure and also for internal exposure. The environmental releases from the NFC facility is well controlled. Soil, water and air from the NFC environment are routinely collected and analysed for all the possible pollutants. The paper describes the Health Physics experience during the last five years on occupational exposures and on environmental surveillance which reveals the high quality of safety observed in our nuclear fuel fabricating installations. (author). 4 refs., 6 tabs